ML20134B587
| ML20134B587 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/30/1985 |
| From: | Lawyer S, Wilson B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20134B583 | List: |
| References | |
| 50-302-OL-85-03, 50-302-OL-85-3, NUDOCS 8508150680 | |
| Download: ML20134B587 (125) | |
Text
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p* REG UNITED STATES f 4/q'o NUCLEAR REGULATORY COMMISSION
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$ j 101 MARIETTA STREET, N.W.
- '* ATL ANTA, GEORGI A 30323
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s ENCLOSURE 1 EXAMINATION REPORT 302/0L-85-03 Facility Licensee: Florida Power Corporation P. O. Box 14042, M.A.C.H-2 St. Petersburg, FL 33733 Facility Name: Crystal River Unit 3 Facility Docket No.: 50-302 Requalification examinations were admi te Crystal River Nuclear Plant near Crystal River, F1 rida.
Chief Examiner: A SantfIawyer '
Date Signed Approved by: . em ff Brpe . Wilson, Section Chief Dath Signed Summary:
Requalification examinations on July 9 - 11, 1985 Written requalification examinations were administered to'eight SR0s and nine R0s; oral requalification examinations were administered to seven SR0s and seven R0s; four of the SR0s and six of the R0s passed these examinations.
This was the last of two scheduled re examinations following the March 1985 Requalification Program evaluation conducted by the NRC. Oral examinations were waived for those three individuals who passed this phase of the requali-fication examinations in March.
The performance on this portion of the requalification examinations (58.8% pass rate) and on the May and July examinations combined (71.0% pass rate) is an indication that corrective actions applied to the Crystal River requalification training program have not been fully effective. Corrective measures to resolve this deficiency will be defined in separate correspondence.
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i REPORT DETAILS l 1. Facility Employees Contacted i
J. Alberdi, Manager-Site Nuclear Operations Technical Services (E)
P. F. McKee, Plant Manager (E).
E. M. Howard, Director, Site Nuclear Operations (E)
T. A. Kamann, Nuclear Operations Records Manager (E)
W. P. Ellsberry, Nuclear Operations Technical Training Supervisor (E)
J. L. Bufe, Nuclear Compliance Specialist (E)
R. Wittman, Operations Superintendent (E)
G. Boldt, Nuclear Plant Operations Manager (R/E)
, L. C. Kelley, Nuclear Operations Training Manager (E) i M. P. Holmes, Nuclear Operations Instructor (R/E)
M.
J. L.F.Springer, Penovich, Nuclear Nuclear Operations Operations TrainingR)Sup(ervisor (E)
Instructor R. C. Zareck, Nuclear Operations Instructor (R)
NOTE: "R" indicates present at examination review i "E" indicates present at exit meeting 1
- 2. NRC Personnel l' i B. A. Wilson, NRC, Region II D. P. Falconer, Jr., NRC - Region II Inspector
- T. F. Stetka, NRC - SRI l *S. Lawyer, NRC, Region II J. C. Huenefeld, PNL B. Gore, PNL i
- Chief Examiner
- 3. Examination Review Meeting i
- At the conclusion of the written examination, the examiners met with l
facility representatives (identified in 1. above) to review the written examinations and answer keys. Specific facility coments and associated i NRC resolution of those comments follow:
NOTE: Connents on questions duplicated between exams are only detailed i once.
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- a. R0 Examination (1) Question 1.19 Facility Comment: Choice (a) should be considered as an acceptable answer since Axial Power Imbalance is DNB related per Tech Spec bases.
NRC Resolution: Agree. This is confirmed on Tech Spec page B.2-5. Answer key changed to accept both (d) and (a).
(2) Question 1.23 Facility Comment: Part (c), acceptable answer should be three pump operation vice three and four pump operation.
NRC Resolution: Agree: Intent is the same, i.e., power level is restricted with only three RCPs operating.
(3) Question 2.6 Facility Comment: Choice (c) is correct instead of choice (d).
NRC Resolution: Agree. This is confirmed by reference STM 2-11.
(4) Question 2.12 Facility Comment: Answer key should reflect upper and lower oil coolers as acceptable terminology for upper thrust bearing and lower guide bearing coolers.
7,RC Resolution: Agree. Any terminology consistent with the purpose of the coolers is acceptable.
(5) Question 2.18 Facility Comment: This question requires memorization of a valve which is human engineered to provide indication in Control Room to indicate to the operator that it is ES controlled.
NRC Resolution: We regard the question as pertinent for the following reasons:
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- 1. A stated learning objective of the PASS was-to " State the administrative requirements associated with the 7
Post-Accident Sampling System."
- 2. The PASS Lesson Plan states that " Tech Specs require that all containment isolation valves that are not included
- in the ES matrix must be closed and :
deenergized."
Only CAV-431 is included on the ES matrix; therefore, all other containment
' isolation valves in the PASS systems must
{ be deenergized during normal operation.
1 i 3. The fact that the valve is singularly i indicated in the control room as an ES l valve should enable any candidate with i control room familiarity to correctly j answer the question.
(6) Question 2.20 Facility Comment: Knowledge asked for is trivial; requires too >
much memorization.
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'{ NRC Resolution: Disagree. The reference provided to the NRC, " Main Steam" system description; lists -
the following as the first two learning objectives:
- 1. Will be able to draw a one-line diagram of the Main Steam System, indicating all major flow paths, major valves and
! numbers.
- 2. Will be able to explain the primary and secondary function.
l We consider the question, which asked to identify the steam supply lines to each of five major components, to fall within these ,
t twoobjectives.
! (7) Question 2.21
) Facility Comment: Answer (c) is not fully correct. Trip condition for MFP is suction valve <60% open 4
, instead of not full open. Choice (5) should
- be acceptable since it will ultimately result i
in a trip of both main FW and booster pumps, a
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- NRC Resolution
- Accept both answers (b) and (c). Choice (b) is supported by reference STM-27-72.
- (8) Question 2.24 E
Facility Comment: A more correct answer may be found in AP-380.
NRC Resolution: A complete answer required the following three sets of valves:
- 1. DHV-11 and 12 l 2. DHV-34 and 35
- 3. DHV-42 and 43 Since the question asked for six valves (instead of three pairs of valves), any i listed in addition to the above were not graded as incorrect.
4 (9) Question 3.5 ,
i Facility Comment: Choice (b) is also correct since actuation of the steam line rupture matrix will shut the MFW Pump Suction Valves which, in turn, will trip both main feedwater pumps. On reset, the crossover valve FWV-28 will auto open if either or both MFW pumps are tripped.
NRC Resolution: Agree. This was confirmed by references
" Main Steam Rupture Matrix" and STM 27-56.
1 (10) Question 3.11 Facility Comment: Gain adjustment of power range channels is an I&C function, not a licensed operator
! function.
NRC Resolution: Granted, however, it is a function that j licensed personnel must be familiar with. -
No change to question or answer key.
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(11)' Question 3.14 Facility Comment: Answer (c) is' correct for 6.9 KV buses, but not for 4.16- KV buses; their breaker opera-tion occurs within 30 cycles. Recommend answer (d) also be accepted or question
- deleted.
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5 NRC Resolution: Elementary diagram B-208-040 provided to i support facility comment. Answers (c) and (d) accepted.
i (12) Question 3.18 1
Facility Comment: All choices except (b) are correct.
Elementary diagram B-208-027 provided to support comment.
NRC Resolution: Comment accepted. System Description was vaguely worded and misinterpreted by examiner.
4 Since three choices were correct, question was
, deleted.
(13) Question 3.22 Facility Comment: The two answers on answer key are incorrect and the following answers should be accepted:
Wide Range Tc (c Id leg)
DH-Hx Outlet Temp. .
NRC Resolution: Surveillance Procedure, SP-422 verifies the above comment. Answer key changed to reflect the above answers. Incore thermocouples was
- also accepted as a correct response since it will provide an RCS temperature indication even though not required by SP-422.
I (14) Question 4.1 Facility Comment: Since the correct answer to Part (a) is NONE, that should be listed in the response column. E NRC Resolution: Verbal clarification was provided during the examination. Response column will include NONE in future examinations. !
(15) Question 4.2 Facility Comment: Answer should be SDV-90 and SDP-7 instead of
NRC Resolution: Typographical errors corrected.
(16) Question 4.5 Facility Comment: Procedure change has been initiated to correct the Remedial Actions of Step 1, AP-380. '
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However, answer key correctly shows the procedural action required by the current revision of AP-380.
NRC Resolution: Responses will be graded according to answer key.
(17) Question 4.8 Facility Comment: If purpote of question is to memorize steps of procedure, it is outside the bounds of required knowledge of licensed personnel.
If the intent is to determine CRD system knowledge, both choices (a) and (b) are correct.
NRC Resolution: Purpose of question was to determine CRD system knowledge. Answers (a) and (b) accepted based on EHC Lesson Plan provided to support comment.
(18) Question 4.18 and 4.19 Facility Comment: Reference for both answers was RP-101.
This document has been replaced by RSP-101.
NRC Resolution: New document dces not change questions or answers. It is the responsibility of Crystal River to provide us with the most current reference material available.
(19) Question 4.20 Facility Comment: Licensed personnel should only be responsible for knowledge of facility administrative limits concerning radiation protection since these are more conservative than 10 CFR 20 limits.
NRC Resolution: Personnel are responsible for knowledge of legal dose limits (10 CFR 20) as well as facility administrative limits. No change to question or answer key.
- b. SR0 Examination l The'following SR0 questions were also on the R0 examination which have I been commented on and resolved in paragraph 3:
7 SR0 Question R0 Question 6.6 2.12 6.9 2.18 !
6.11 2.21 6.12 2.24 6.17 3.5 6.19 3.14 6.20 3.18 7.1 4.1
- 7. 2 4.2 7.4 4.5 7.19 4.18 7.20 4.19 7.21 4.20 (1) Question 5.21 Facility Comment: The reference used on the answer key was questioned.
NRC Resolution: The reference is a 1979 submittal from Crystal River which was based on the B&W generic Small Break LOCA analysis. The information contained in it is still relevant.
(2) Question 7.16 Facility Comment: Bypassing the RCP Power Monitors is no longer required. Reference, if applicable, should be OP-204 instead of OP-210.
NRC Resolution: Step 4.14 of OP-210, " Reactor Startup",
Revision 16, contains the information addressed in this question. This pro-cedure was part of reference material package supplied by Crystal River. No change to question or answer key.
(3) Question 8.22 Facility Comment: Wording of question is confusing. It is difficult to figure out what question is asking.
NRC Resolution: Question was very close to verbatim from reference. No candidate expressed any concern over the wording to the examiners during conduct of the examination. No change to question or answer key.
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- 4. Exit Meeting At the conclusion of the site visit, the examiners met with representatives of the plant staff to discuss the results of the examinations. Those indi-viduals who clearly passed the oral examination were identified.
There were no generic weaknesses noted during the oral examination. The cooperation given to the examiners was noted and appreciated. The licensee did not identify as proprietary any of the material provided to or reviewed by the examiners.
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101 MARitTTA STIE ET.C.CJ.
ATLANTA,0EORGIA 30303
,,,,, ENCLOSURE 3 (1 of 2)
U. S. NUCLEAR REGULATORY C0fEISSION REACTOR OPERATOR REQUALIFICATION EXAMINATION Facility: Crystal River Reactor Type: B&W Izz Date Administered: July 9, 1985 Examiner: S. Lawyer Candidate:
INSTRUCTIONS TO CANDIDATE:
Use separate paper for answers. Write answers on one side only. Staple question sheet on top of the answer sheets. Points for each question are indicated in parenthesis after the question. The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up four (4) hours after the examination starts.
% of Category % of Candidate's Category Value Total Score Value Category 25 1. Principles of Nuclear Power Plant Operation, Thermodynamics, Heat Transfer and Fluid Flow 25 ?. Plant Design Including Safety and Emergency Systems j 14 j#~ 3. Instruments and Controls 25 4. Procedures - Normal.
Abnormal, Emergency, and Radiological Control TOTALS
% 30(f Final Grade %
All work done on this examination is my own. I have neither given nor received I aid.
l Candidate's Signature
1.0 PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, (25.0)
HEAT TRANSFER AND FLUID FLOW 1.1 When xenon is in equilibrium, the iodine formed equals the iodine (1.0) lost and the xenon formed equals the xenon lost. Select the CORRECT statement concerning the xenon equilibrium balance equations.
- a. Most of the iodino formed is coming directly from fission.
- b. Most of the iodine lost is a result of its neutron absorption loss.
- c. Most of the xenon formed comes directly from fission.
- d. Most of the xenon lost is a result of its neutron absorption loss.
1.2 Over core life, the reactor becomes more responsive for a given (1.0) reactivity change due to: (Choose One)
- a. Pu2 causing an increase in Beff.
- b. Pu28' causing a decrease in Seff.
- c. Pu2 ** causing an increase in Beff.
- d. Pu causing a decrease in Beff.
1.3 During fuel loading, which of the following will have NO effect (1.0) on the shape of a 1/M plot?
- a. The location of the neutron sources in the core.
- b. The strength of the neutron sources in the core.
- c. The location of the neutron detectors around the core.
- d. The order of placement of fuel assemblies provided the proper enrichments are placed in their proper location.
1.4 Which one of the following factors will hinder natural circulation?
(1.0)
- a. Reduction of turbine bypass valve setpoint.
- b. Increase in OTSG 1evel. j
- c. Reduction of feedwater temperature.
- d. Decrease in decay heat.
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1.5 During a reactor startup, power is being raised above the point of (1.0) adding heat (POAH). Which of the following statements is CORRECT?
(Assume a linear reactor power increase to about 3% power)
- a. Since header pressure is 885 psig, Tave will not rise above the corresponding saturation temperature of 532*F.
- b. Since the OTSGs are low level limited and header pressure is being maintained at 885 psig, Tave will rise and the steam temperature will tend to follow Th.
- c. With the header pressure being maintained at 885 psig, the OTSGs will remain at saturated conditions and no superheat will be added.
- d. Since the OTSGs are low level limited, the steam is superheated at zero power conditions and rises proportionally with power.
1.6 A general rule is often stated " doubling the count rate halves the (1.0) margin to criticality." This is mathematically stated by the equation.
CR1 = 1-keff 2 CR2 1-keff 1 Which one of the following statements is CORRECT concerning the above statement and equation?
- a. Both keffl and keff2 have to be less than 1.0
- b. Equal changes in keff result in equal changes in subcritical multiplication level.
- c. The equation only approximates the instantaneous change in count rate; once equilibrium value is reached, the count rate will be higher.
- d. A second doubling of the count rate will result in the reactor becoming critical or supercritical.
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3 1.7 OP-210, " Reactor Startup", requires that the critical rod position (1.0) be taken at 10 ' amps on the intermediate range. If, during a xenon free reactor startup at MOL, the operator " overshot" 10 ' amps and instead leveled off at 10 ' amps, which of the following statements is CORRECT?
- a. At 10 ' amps, there are little or no effects from nuclear heat but since the reactor is a decade higher in power, the critical rod position would be higher.
- b. At 10 ' amps, there are little or no effects from nuclear heat; therefore, the critical rod position should be the same as at 10 ' amps.
- c. At 10 ' amps there are substantial effects from nuclear heat; therefore, the critical rod positions will be higher than at 10 8 amps.
! d. At 10 7 amps, nuclear heat, xenon and the decade higher in power level will result in a higher critical rod position.
1.8 The reactor trips from full power, equilibrium xenon conditions. (1.0)
Six hours later the reactor is brought critical at 10 ' amps on the intermediate range. If power level is maintained at 10 ' amps which of the following statements is CORRECT concerning control rod motion?
- a. Rods will have to be withdrawn since xenon will closely follow its normal build-in rate.
- b. Rods will have to be inserted due to xenon decay.
- c. Rods will have to be rapidly inserted since the critical reactor will cause a high rate of xenon burnout.
- d. Rods will approximately remain as is as the xenon establishes its equilibrium value for this power level.
1.9 Figure 6.2-3 shows a graph of pump laws i.e., the relationship (1.0) between pump speed and other pump parameters. Which one of the following parameters is represented by curve 2?
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, ,a. Power
- b. Flow Rate
- c. Voltage
- d. Discharge Pressure
4 1.10 Startup of a centrifugal pump with the discharge valve shut (1.0) is best characterized by which one of the following?
- a. high motor current and high discharge pressure
- b. 1;w motor current and low discharge pressure
- c. low motor current and high discharge pressure
- d. high motor current and low discharge pressure 1.11 Figure 43, " Surface Utilization vs Flow," represents the heat (1.0) transfer process in your OTSGs. Which of the following state-ments is CORRECT concerning Departure from Nucleate Boiling
- (DNB) Ratio as it relates to this Figure?
- a. DNBR of 1.0 occurs prior to nucleate boiling and cannot
, be shown on this figure.
- b. DNBR of 1.0 occurs between the nucleate boiling and the I
film boiling areas.
- c. DNBR of 1.0 occurs between the film boiling and the superheat areas.
1.12 With the main steam temperature and pressure at 636*F and (1.0) -
885 psig respectively, a main steam relief valve seat begins to leak to atmospheric pressure. The temperature of the steam three feet out of the relief valve is approximately:
- a. 636 F
- b. 500*F
- c. 444*F
- d. 212*F 1.13 Concerning the behavior of samarium-149, in the reactor, which (1.0) l of the following statements is CORRECT?
- a. Most of the Se produced comes directly from fission.
- b. Most of the removal of Sm is by radioactive decay,
- c. Sm reactivity is independent of flux once it has reached equilibrium.
- d. Equilibrium Sm is reached about 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> after the initial startup of the reactor.
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5 j 1.14 Given the power history shown on Figure 2 attached, select (1.0) the most accurate curve displaying the expected xenon history.
a.
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c.
d.
1.15 The reactor is being shutdown. A stable neutron decay rate of (1.0)
-78 seconds (-1/3 DPM SUR) has been established from the point at which both intermediate range channels read 5 x 10 ' amps. One intermediate detector is properly compensated, the other is undercompensated. Select the CORRECT statement concerning reset of the SRM high voltage bistable.
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- a. The bistable will reset in about six minutes.
- b. The bistable will reset in longer than six minutes due to the undercompensated detector.
- c. The bistable will reset in shorter than six minutes due to the undercompensated detector.
- d. The backup from the power range channels will reset the bi table in about six minutes.
1.16 An estimated critical boron concentration of 500 ppm was calculated using the information on Worksheet II (attached).
Assume the. reactor achieved criticality at 80% withdrawn on Group 7. How would this critical rod position change (Group 7 more inserted, more withdrawn or no change) if each of the following conditions were different from that on Worksheet II?
Assume no boron change and consider each condition separately.
- a. Line 2.2.a. Last power level was 50% FP for 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. (.5)
- b. Line 2.2.b. Time shutdown was 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. (.5)
- c. Line 4.a. Average RC Temperature was 532*F. (.5)
- d. Line 5. Group 8 0 0% WD. (.5)
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1.17 Which one of the following statements about condenser vacuum is (1.0)
CORRECT?
- a. The pressure difference between the actual vacuum and absolute zero is termed condensate depression.
- b. The pressure differencc between the actual vacuum and MSR outlet is termed LP turbine back pressure.
- c. By operating at a vacuum, the condenser permits steam at about 80'F to be exhausted from the turbine; without a vacuum, the steam would be at 212*F.
- d. As condenser vacuum decreases, cycle efficiency decreases but turbine exhaust steam temperature is not affected.
1.18 The Main Steam Line Break Accident forms the basis for the Shutdown (1.0)
Margin requirement at End-of-Life (EOL) conditions because:
- a. Beta-effective is at its maximum value.
- b. MTC is at its most negative value.
- c. Control rod insertion limits are most restrictive.
- d. Hot channel factors are at the most conservative values.
1.19 Which one of the following is one of the DNB related parameters (1.0) that must be maintained with'n Tech Spec limits?
- a. axial power imbalance
- b. regulating rod insertion limits
- c. regulating rod group overlap
- d. pressurizer pressure 1.20 The process of hydrogen generation'in the reactor building after (1.0) a LOCA which is controlled by the addition of caustic (NaOH) is:
- a. Radiolysis
- b. Zirc-water Reaction
- c. Hydrogen coming out of solution
- d. Zinc-boric acid Reaction
7 1.21 Which of the following statements about pump Net Positive Suction (1.0)
Head (NPSH) is CORRECT?
- a. NPSH is the amount by which the saturation pressure is greater than the suction pressure for the water being pumped.
- b. When a pump is started, the NPSH will decrease by the amount of the pressure drop in the suction piping.
- c. NPSH is essential for operation of centrifugal pumps but not for positive displacement pumps.
- d. NPSH can be calculated by subtracting the suction pressure from the discharge pressure.
1.22 Which statement best characterizes Natural Circulation? (1.0)
- a. It needs a pump to get started.
- b. The elevation of the heat source must be above that of the heat sink.
- c. The driving force is a difference in density.
- d. Heat transfer is more efficient if steam or gas is mixed with water.
1.23 Refer to Figure 2.1-2, " Reactor Core Safety Limit." Identify (2.0) by name or title the p&rts of the Figure marked A, B, C, and D.
END OF SECTION 1
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2.0 PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS (25.0) 2.1 Which of the following statements concerning the reactor (1.0) building isolation and cooling system (RBI & CS) interlocks is CORRECT?
- b. Only two of the three channels of actuation are required to be bypassed by the system logic for the operator to regain control of all components actuated by the RBI & CS.
- c. Once a component has been actuated to its ES position, it will remain in that position except the RB fans which can be shifted to FAST speed if required.
- d. The RBI and CS actuation will override any other signal except the control signal.
2.2 Select the INCORRECT statement concerning the Chilled Water (1.0)
System.
- a. The system supplies low temperature water to the Control 4
Complex Air Handlers, Post Accident Sampling Coolers, Penetration Air Handlers, and Switchgear Room.
- c. The Water Chiller units can be cooled by either Nuclear Services Closed Cycle Cooling or Secondary Services Closed Cycle Cooling.
- d. Under accident conditions, only the Control Complex Air Handler cooling function is required to be operable.
2.3 Select the CORRECT statement concerning the Heater Drain (1.0) and Vent System.
- a. The only heater drain valves that have control switches on the Main Control Board are the high level dumps for the MSR HP flash tanks and the high level dumps for the MSR LP Flash Tanks.
- b. A high level in the IA, IB, 2A, and/or 2B heaters will trip the main turbine.
- c. All condensate and feedwater heaters have extraction steam non-return valves to prevent damage to the LP turbines.
- d. When the main turbine trips, the high level dump valves on all condensate and feedwater heaters open and dump to the main condenser.
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9 2.4 Which one of the following parameters is changed to vary (1.0) condensate pump speed?
- a. Motor input voltage
- b. Motor / pump coupling
- c. Motor frequency
- d. Motor / bus phase 2.5 The design feature of the Reactor Coolant Pumps at Crystal (1.0)
River which prevents exceeding the minimum DNBR limit on a total loss of AC power to the pumps is the:
- a. anti-reverse rotation device
- b. flywheel
- c. Kingsbury double acting thermal bearing
- d. adequate RCP seal injection 2.6 Which one of the following statements is CORRECT regarding (1.0) the hazards of letting an OTSG boil dry?
- a. The shell becomes hotter than the tubes which can lead to tube buckling.
- b. The shell becomes hotter than the tubes which can lead to exceeding yield stress in the tubes.
- c. The tubes become hotter than the shell which can lead to tube buckling.
- d. The tubes become hotter than the shell which can lead to exceeding yield stress in the tubes.
2.7 What design feature of the ECCS limits the amount of (1.0) zirconium hydride reaction under accident conditions?
- a. Limiting the temperature of the fuel.
- b. Use of only zirconium oxide (no metalic zirc).
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- c. Eliminate hydrogen from the vicinity of the fuel clad.
l d. Maintain pH basic (7.2-11.0).
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10 2.8 Which of the following statements concerning the Core (1.0)
Flood (CF) system during normal plant operation is CORRECT?
- a. When increasing CFT pressure by nitrogen addition, the nitrogen heater must be energized ten minutes or more prior to establishing nitrogen flow to prevent condensation,
- b. High core flood tank pressure may be relieved by venting to the Reactor Building.
- c. The preferred method of decreasing the CFT water level is by draining to the RC drain tanks.
2.9 The synchronizing pin and bearing in the upper portion of the rotor (1.0) tube in the Control Rod Drive Mechanism (CRDM) is used to ensure...
- a. uniform rod speed over full travel
- b. proper direction of rotation
- c. both segment arms move together
- d. correct place relationship between individual rods within a group.
2.10 Which one of the following components of the EHC control oil (1.0) system are provided to maintain system pressure at approxi-mately 1250 psi?
- a. Unloader valves
- b. Relief valves
- c. High pressure accumulators
- d. Pressure switches
11 2,11 With regard to the Reactor Building Spray System, which one (1.0) of the following statements is CORRECT?
- a. Full post-accident heat removal capability is provided by the RB Spray System and at least one RB Emergency Cooling Unit.
- b. The NaOH additive lowers the pH of the borated water into the acidic range to remove airborne iodine in the RB atmosphere.
- c. A single pressure-vacuum relief valve on the Na0H tank provides both overpressure and excessive vacuum protection.
- d. The RB spray pumps are cooled by Nuclear Services Closed Cycle Cooling.
2.12 The Nuclear Services Closed Cycle Cooling System supplies (1.0) four separate coolers on each Reactor Coolant Pump and Motor.
LIST these four coolers.
2.13 Which one of the following plant ventilation fans is operated (1.0) from its local control station (as opposed to operation from the control room)?
- a. Turbine building ventilation supply fan (AHF-25A).
- b. Steam generator compartment fan 3A(AHF-4A).
- c. Spent fuel pool supply fan (AHF-23A).
- d. Intermediate building ventilation exhaust fan (AHF-29A).
2.14 Which one of the following makeup pump lube and gear oil system pumps (1.0) has NO auto start provision?
- a. Main lube oil pump
- b. Main gear oil pump
- c. Backup gear oil pump
- d. Backup lube oil pump
12 2.15 Select the CORRECT statement about the makeup and purification (1.0) system radiation monitoring,
- a. Since RML-1 is upstream of the connection with the DHR system, it is inoperable when the letdown system is used
'in connection with the DHR system.
- b. RML-1 is an ionization detector installed in the letdown line,
- c. After leaving RML-1, the letdown passes through a 750 ft.
delay coil to allow N2' to decay out.
- d. The letdown flow from RML-1 re-enters the makeup system upstream of the post filters.
2.16 Which one of the following statements is CORRECT regarding the (1.0) design of the emergency diesel generator air start system?
- a. There are two valves, one manual and the other remotely operated, in the interconnecting line between the two diesel air start systems,
- b. The manual air shutoff valve between the air reservoirs and its starting air manifold is provided with an alarm switch which actuates whenever the valve is not fully open.
- c. An air pressure low alarm (APLA) pressure switch alarms at 150 psig decreasing and auto starts the DC compressor motor,
- d. The pressure switch that auto starts and stops the AC motor (at 225 psig and 250 psig respectively) does not function when the DC motor is used; the DC motor must be started and stopped manually.
2.17 The internal vent valves are installed in the core support shield (1,0) to prevent a pressure imbalance following which accident?
I
- a. Ejected rod j l
- b. Cold leg LOCA
- c. Hot leg LOCA
- d. S/G tube rupture l
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13 2.18 Fou* Post Accident Sampling System (PASS) containment isolation (1.0) valves are circled on the attached Figure 3. Of these, all but one must be deenergized during normal operation. Which one?
- a. CAV-429
- b. CAV-430
- c. CAV-431 j
- d. CAV-432 2.19 Select the CORRECT statement concerning the Diesel Generator fuel (1.0) oil system.
- a. Sufficient fuel oil is stored in each unit's day tank for approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at name plate rating.
- b. The two 30,000 gallon fuel oil storage tanks have a double valve connection between them to provide additional fuel capacity to either diesel generator unit.
- c. Both fuel oil transfer pumps on each DG are DC powered to provide redundancy in case of a station blackout.
- d. Care must be taken when filling the day tank from a storage tank since the day tank overflows to the waste system.
2.20 There are four main steam lines designated A-1, A-2, B-1 and B-2. (2.0)
For each of the following systems or steam supplies, LIST the appropriate steam line(s).
- a. Emergency Feed Pump
- b. Main FW Pump 3A
- c. Turbine bypass (steam to condenser)
- d. Deaerator 1
- e. Atmospheric dump valves 2.21 Which of the following trip conditions is common to both a main (1.0) feedwater pump and a feedwater booster pump? (Remember: trip condition, not signal).
- a. Overspeed
- b. Low deaerator level 1
- c. Suction valves not full open l l
- d. Main steam line rupture matrix actuation
14 2.22 Which one of the following normal manual operations is NOT (1.0) provided for the three fire pumps? <
- a. start from control room
- b. start from pump house
- c. stop from control room
- d. stop from pump house 2.23 Match the Engineered Safeguards channel or NI&P Channel with its (1.0) appropriate color.
- a. ES Channel A or 1. Blue or black with blue NI&P channel I stripe
- b. ES Channel B or 2. Brown or black with brown NI&P channel 2 stripe
- d. NI&P channel 4 4. Red or black with red stripe
- 5. Yellow or black with yellow stripe 2.24 In the long term, following a SBLOCA, the BWST has reached its (1.0) lo-lo level alarm setpoint, but RCS pressure has remained above the shutoff head of the LPI pumps. LIST the sequence of valve manipulations (by name or number) that are necessary to set up the LPI and HPI systems for continued injection into the RCS. (Six valves r'equired.)
END OF SECTION 2
O t 15 3.0 INSTRUMENTS AND CONTROLS (25.0) 3.1 Which one of the following load limiting conditions and (1.0) corresponding load limit is CORRECT for loss of one RC pump at full power?
- a. 30%/ min to maximum limit of 75%.
- b. 30%/ min to maximum limit of 45%.
- c. 50%/ min to maximum limit of 75%.
- d. 50%/ min to maximum limit of 45%.
3.2 If both of the lights on a Bailey meter hand / auto control (1.0) station are lit:
- a. The station will control in either auto or manual, whichever was last selected.
- b. The station will not control in either auto or manual.
- c. The station will control in auto since auto overrides when both are selected.
- d. The station will control in manual since manual overrides when both are selected.
3.3 Which one of the following statements concerning the Control Rod Drive Position Indication System is CORRECT? (1.0)
- a. The 0% switch is located 1.5 inches above the in-limit switch.
- b. The 100% switch is located 1.5 inches above the out-limit switch.
- c. The first rod in any group to reach the 100%
switch will stop further travel of all rods in that group.
- d. When actuated, the out-limit switch will generate an out-inhibit condition on the Diamond Panel.
l l
16 1
3.4 Which of the following statements concerning the decay heat (DH) (1.0) system suction valves, CHV-3, 4 and 41 is CORRECT?
- a. All three valves have local control pushbuttons on their respective breakers in addition to a control switch on the control room ES Panels,
- b. Only DHV-3 and DHV-4 have local control pushbuttons although all three valves have control room control switches.
- c. An interlock prevents opening all three valves when RC pressure is >330 psi.
- d. An interlock prevents opening DHV-3 and 4 at 300 psi while DHV-41 is set for 330 psi.
3.5 Select the CORRECT statement concerning the FW Pump Discharge (1.0)
Crossover Valve, FWV-28.
- a. During normal full power operation, the valve is open with its control switch in AUTO position.
- b. On reset of the steam line rupture matrix it will auto-matically open.
- c. It will auto close on actuation of either steam line rupture matrix or ES channels A and B.
_d. The auto open signal comes from a pressure switch on the main feedwater pump control oil pressure.
3.6 a. LIST by name or number the valves that will be isolated (2.0) following actuation of the Steam Line Rupture Matrix.
Consider either OTSG.
- b. What are the two conditions, either of which must be (1.0) satisfied in order to reopen any of the isolated valves?
3.7 A synchroscope moving slowly in the SLOW direction (counter- (1.0) clockwise) indicates which of the following?
- a. Machine frequency higher than bus frequency, phases not matched.
- b. Machine frequency lower than bus frequency, phases not matched.
- c. Machine voltage higher than bus voltage, currents not in phase.
- d. Machine voltage lower than bus voltage, currents not in phase.
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17 3.8 Which of the following statements is CORRECT concerning the (1.0) source range channels?
- a. The source range signals originate in two high sensitivity BF detectors that operate in the proportional range.
3
- b. Tne detectors are surrounded by lead shielding, thus making gamma compensation unnecessary.
- c. Due to the low level pulses from the detectors, preamplifiers located in the RPS cabinets are required to provide impedance matching.
- d. Due to their sensitivity, long term outages will have no noticeable effect on the range of indication.
3.9 Assume the reactor tripped on high Th of 618 F. After Th (1.0) stabilized at a lower value (550'F) what would you expect to see on the Output State Lamp and Output Memory Lamp for the Th bistables in each RPS cabinet?
- a. both lamps dim
- b. both lamps bright
- c. Output State Lamp - dim Ouput Memory Lamp - bright
- d. Output State Lamp - bright Output Memory Lamp - dim 3.10 The gas channels on the atmospheric monitoring channels, when (1.0) alarmed, would be more indicative of an instantaneous release of radioactivity than would the particulate or iodine channels.
What is the reason for this statement?
3.11 Which one of the following functions is NOT served by the (1.0) power range nuclear instrument bistable module.
- a. Over power trip $5% full power.
- b. Rod withdrawl hold bypass at 10% full power.
- c. Source range detector high voltage cut off at 10%
full power.
- d. Power range gain adjustment at 50% full power.
18 3.12 If an operator mistakenly sets the low load limit high (=85%) and an asymmetric rod runback occurs while at 100% power, which of the following would occur? (1.0)
- a. Demand would decrease to 55%
- b. Demand would decrease to 60%
- c. Demand would decrease to 85% of 55% F.P.
- d. Demand would decrease to 60% of 85% F.P.
3.13 Each area radiation monitoring channel has a remote local readout, (1.0) for example, the readout module near the personnel access hatch on elevation 132 (RM-G9). Select the correct statement concerning this remote local readout module.
- a. In the event that the control room readout module malfunctions which causes its meter to read incorrectly, you may be able to determine the correct reading from the meter on the elevation '
132 module.
- b. The alarm reset pushbutton on the elevation 132 module will reset any previous alarms provided the input is below the alarm setpoints.
- c. The elevation 132 module will indicate " warning" and "high" alarms but not " failures".
90
- d. Only the control room module contains a Sr check source.
3.14 During a " rapid Dus transfer", which one of the following source (1.0) feeder circuit breaker operations will occur (within 6 cycles)?
- a. both the outgoing and the incoming will close
- b. both the outgoing and the incoming will trip
- c. the outgoing will trip and the incoming will close simultaneously
- d. the outgoing will trip before the incoming will close
- e. the outgoing will trip after the incoming closes 3.15 Which one of the following states the method of powering the (1.0)
" safeguard communication system"?
- a. 120 VAC vital bus 3A
- b. 480 VAC ES bus 3B2
- c. 125/250 VDC Bus 3B
- d. sound powered phones
- e. dual input inverter 3E
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19 3.16 Which one of the following is NOT part of the POWER / IMBALANCE / (1.0)
FLOW TRIP Circuitry?
- a. Hammel-Dahl flow tube
- b. Square root extractor
- c. Buffer amplifier
- d. Optical Isolator 3.17 Which one of the followina statements is CORRECT concerning (1.0) the EHC control panel operation?
- a. When the throttle pressure controller IN button is depressed, the throttle and governor valves will run back to their fully closed position if the throttle pressure is less than the set point,
- b. When the oper. integ. control system button is depressed, if there is a pressure difference of +50 psi from the normal control set point (885 psi), the EHC control system will automatically revert to the oper.
auto mode.
- c. When the oper. auto sync button is depressed with the unit within 50 rpm of synchronized speed, the EHC control system will close both output breakers when the correct conditions of phase and speed are attained.
- d. When the oper manual button is depressed, the valve position limit is no longer in effect.
3.18 Which one of the following choices of depressing STOP push- - ( 1. 0 ) -
buttons will, by itself, trip the diesel generator output breaker?
Ikb a. stop pushbutton in the control room gqr b. one stop push button on the diesel gaugeboard
- c. both stop push buttons on the diesel gaugeboard
- d. stop pushbutton on the diesel generator local control panel by the D-G air start compressor
20 3.19 With regard to the pressurizer heater control circuits, (1.0) if under normal operation, the pressurizer level drops to less than 40", which of the following indications would occur?
- a. white indicating light on bank D heater will go out
- b. white indicating light on bank C heater will go out
- c. red indicating light on bank D heater will go out
- d. red indicating light on bank C heater will go out 3.20 Which one of the following is CORRECT concerning the (1.0)
" Sequence - Inhibit lamp (amber)"?
- a. When it comes on, it also generates an "Out-Inhibit" signal.
- b. This indication will be on until all safety groups are withdrawn to the out-limit.
- c. Sequence monitor No. 1 provides a fault indication when the groups are inserting or withdrawing out of sequence in the manual mode,
- d. This lamp is controlled by two sequence monitors, utilizing Groups 5, 6, and 7 Absolute Position Indication (API) average signals.
3.21 Which of the following indications warn that the feed selector (1.0) handle should NOT be pulled up?
- a. " Bleed Mode 84 and 85 selected" white light lit
- b. " Waste disposal bleed permit" white light lit
- c. "CAV-57 open" white light lit
- d. both " bleed mode B4 or B5 selected". white light and " waste disposal bleed permit" white light lit
21 3.22 a. During a plant cooldown using OP-209 " plant cooldown", it (1.0) requires that the cooldown rate be restricted. Complete the following table with the CORRECT temperature and cooldown rates.
RCS Temperature Change in any RCS Temperature (T) Cooldown Rate One Hour Period T> (1) (2) *F/HR (2) *F (1) *F>T> (3) *F (4) *F/HR (4) *F (3) *F > T (5) F/HR (5) F
- b. LIST two different sources of RCS temperature for monitoring (1.0) the above cooldown rates, i.e., what two temperatures in the RCS can be read to verify that you are within the above limits?
END OF SECTION 3
{ I
22 4.0 PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL (25.0) 4.1 The Immediate Actions, in response to High Alarms from Atmospheric (2.5)
Radiation Monitors RM-Al through RM-A5, require you to "enst-stopped" various ventilation fans. Match the fans you are . quired to ensure stopped with the appropriate monitor and procedure.
NOTE: Some fans may be required in more than one procedure.
- a. RM-Al (AP-241) 1. AHF-9A & 9B
- b. RM-A2 (AP-242) 2. AHF-10
- c. RM-A3 (AP-243) 3. AHF-11A and 11B
- d. RM-A4 (AP-244) 4. AHF-17A and 17B
- e. RM-A5 (AP-243) 5. AHF-19A and 19B
- 6. AHF-20A and 208 (or in slow speed)
- 7. AHF-30
- 8. AHF-34
- 9. AHF-44A and 448 4.2 List your immediate actions in response to an alarm from RM-L7. (0.5) 4.3 Which of the following is an immediate action required (1.0) in AP-320, " Loose Parts monitoring system".
- b. Notify I&C technician to remove the LPMS tape deck.
- c. Adjust "FS range" switch on affected channel signal amplifier until alarm clears.
- d. Select the alarming channels to " audio matrix" position.
4.4 An alarm on which one of the following radiation monitors (1.0) would be an indication of loss of decay heat removal?
- a. RM-A3
- b. RM-A4
- c. RM-A5 .
l
- d. RM-A6
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23 4.5 The following is the first immediate action under AP-380, (1,0)
" Engineered Safeguards system actuation". IF SRMA present OR RC PRESS < 1500 psig, THEN depress "HPI Actuation" Pushbutton "X" and "B". What are the Remedial Actions associated with this step?
4.6 LIST your Immediate Actions to AP-450, " Emergency Feedwater (2.0)
Actuation."
4.7 The nuclear services cooling water to the CRD stators should (1.0) be secured under which of the following conditions,
- a. Less than three stators are energized and the reactor is NOT critical.
- b. RC system temperature is between 200*F and 300*F.
- c. Air temperature around the drives in the service structure is less than 150 F.
- d. Any time all CRDs are deenergized for an extended geriod of time.
y (w Of- G b 4.8 To accomplish CRD safety group latchingAwhich one of the (1.0) following shows the proper order in whi6h the actions should be-taken?
- a. Press " trip reset"; press " fault reset"; and reset
" reactor tripped".
- b. Press " trip reset"; reset " reactor tripped"; and press " fault reset".
- c. Press " fault reset"; press " trip reset"; and reset
" reactor tripped".
I d. Press " fault reset"; reset " reactor tripped"; and press
" trip reset".
4.9 If OTSG's are available, Step 14.a of AP-380 (see Figure 5 & 6 (1.0) attached) requires the starting of a number of RCPs in a particular loop configuration. (NOTE: Some information has been deleted from Figure 5 & 6). If the RC pressure is 300 psi and RC. temperature (Tc) is 300*F, you should:
- a. start one pump in either loop
- b. start one pump in each loop
- c. start two pumps in either loop
- d. start two pumps in each loop
- e. Refer to AP-530
e 24 4.10 Annunciator Window I-2-3 on the ICS Panel is labeled " Pressure (1.0)
Transient in Progress." Which one of the following is a CORRECT indicated condition for this annunciator?
- a. Pressurizer Safety Valve Open
- b. High RC pressure at low temperature (NDTT)
- c. High RCS pressure (above trip setpoint)
- d. HPI Actuation on low RCS pressure 4.11 ICS procedure, OP-501 states in part, "If operating signal source (1.0) malfunctions make signal source transfer necessary, transfer to another signal source should be done ... " Which one of the following CORRECTLY completes this statement?
- a. immediately after placing the affected ICS station in HAND.
- b. immediately, regardless of ICS operating mode.
- c. only after checking the computer for a valid alternate signal and placing the affected ICS station in HAND.
- d. only after checking the computer for a valid alternate signal; affected ICS station may be in HAND or AUTO.
4.12 Where would you expect to find the correct procedure for (1.0) adding lithium hydroxide (LiOH) to the makeup system?
- a. OP 202 - Plant heatup
- b. OP 304 - Soluble poison concentration control
- c. OP 402 - Makeup and purification system
- d. OP 403 - Chemical addition system 4.13 Of the following maneuvering restrictions during power escalation, (1.0) one applies ONLY at cycle startup. Which one?
- a. Below 20% FP power escalation is limited to 10%/hr.
- b. From 90 to 95% FP power escalation is limited to 10%/hr.
- c. Above 40% FP power escalation is limited to 3%/hr.
- d. Hold at 75 2% FP for a 5-hour soak.
1
r i 25 4.14 Which one of the following is an appropriate "immediate" action (1.0) according to EP-120, " Inadequate Shutdown Value?"
- a. Stop cleanup.
- b. Establish letdown flow to MUT > 40 gpm.
- c. Start boric acid pump CAP-3A or 3B.
- d. Verify reactor trip, go to VP-580.
4.15 Which one of the following is CORRECT concerning the operation of (1.0) the ICS main feedwater pump speed control station?
- a. Tripping of the associated feedwater pump will inhibit
" auto" operation and light both " auto" and " hand" lamps.
- b. Care should be taken when simultaneously transferring both Loops "A" and "B" main feedwater pump control stations to " auto".
- c. " Meas-VAR" position indicates feedwater demand error when the main block valves are shut.
4.16 Which one of the following is a CORRECTLY stated Limit and (1.0)
Precaution as contained in OP-605, "Feedwater System".
- a. If at any time emergency FW pump discharge drops to zero pressure, immediately secure the pump under all operating conditions.
- b. If at any time emergency FW pump discharge drops to to zero pressure, immediately secure the pump, except under emergency operation.
- c. The motor-driven emergency FW pump (EFP-1) will not auto-start if emergency diesel generator 3B (EDG-38) is running and closed onto its respective bus.
- d. The motor-driven emergency FW pump (EFP-1) will not auto-start if emergency diesel generator 3B (EDG-38) is running with its output breaker open.
r 26 4.17 An Immediate Action to AP-770, " Emergency Diesel Generator (1.0)
Actuation" is:
IF under voltage exists on 4160V ES bus, then ensure affected bus is energized by EDG.
What are the Remedial Actions associated with this step?
4.18 Which one of the following " Radiation Area" definitions (1.0) means the same as that given in RP-101, " Radiation Protection Manual"?
- a. any area where the dose rate exceeds five mrem /hr or where, in any five (5) consecutive day period, exceeds 100 mrem /hr at any time.
- b. any accessible area where a major portion of the body could exceed a dose of five mrem in any one (1) hour, or in any five (5) consecutive days a dose in excess of 100 mrem.
- c. any accessible area where any portion of the body could exceed a dose rate of five mrem /hr or where, in any five (5) consecutive day period, could exceed a dose rate of 100 mrem /hr at any time.
- d. any area where the dose rate to any portion of the body could exceed a dese of five mrem in any one (1) hour, or in any five (5) consecutive days a dose in excess of 100 mrem.
4.19 Which one of the following provisions is the responsibility (1.0) of a reactor operator leaving the 95' elevation control complex RCA as part of the first step in his whole body frisk?
- a. Ensure the equipment is turned on and operating on the highest scale.
- b. Ensure proper operation of the instrument by noting that the instrument has been source checked.
l
- c. The background reading should be less than 300 dpm/100 cm2,
- d. Ensure the beta window control is in the open position. l l
r 27 4.20 Which one of the following is CORRECTLY stated regarding a permis- (1.0) sible dose to an operator in a restricted area as specified in 10CFR 20.
- a. Under non-accident conditions, the operator is permitted to receive no more than 7h rems per calendar quarter to each hand and to each foot.
- b. Under non-accident conditions, the operator is permitted to receive no more than I rad of beta per calendar quarter to the lens of the eye.
- c. Under accident or emergency conditions, the operator is permitted to receive up to 25 rem once in a lifetime exposure.
- d. Under accident or emergency conditions, the operator is permitted to receive up to 100 rem once in a lifetime exposure.
4.21 TRUE OR FALSE
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- a. When performing procedural actions, you are required to have (0.5) and follow the " Working Copy" of all ops used regardless of how frequently the procedure is performed.
- b. Unlicensed plant management personnel, not in a training (0.5) status, are allowed to manipulate the controls only under the direction and in the presence of a licensed operator or senior operator.
- c. In an emergency affecting the safety of operations, the (0.5)
" Operator at the Controls" may momentarily leave the red-carpeted area to respond to annunicators o.. back panels (ventilation panel for example).
- d. Reacing the Shift Supervisors Log and Control Center log by (0.5) the oncoming Reactor Operator may be accomplished immediately after shift turnover.
e 28
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4.22 According to EP-290, " Inadequate Core Cooling", the hot leg vents (1.0) should be used under two separate conditions. Which of the following choices states those conditions. (See page 7 of EP-290 attached for reference to " Regions").
- a. Pzr press >1500 psig; press and temperature in Region 2
- b. Pzr press >1500 psig; subcooling margin <50'F
- c. Pzr press >1500 psig; press and temperature in Region 3
- d. Pzr press >2300 psig; subcooling margin <50 F
- e. Pzr press >2300 psig; press and temperature in Region 3 END OF SECTION 4 END OF EXAM l
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} -}
. /F/d a y F ( Vt 1 hr % a '/ %Fr ' .%)? ( / FR y, . , . '
( w n / >n. .}
/ /t N/ ,
ur/i A / / >(/s/i A'/ /% ldI l g 9
f/ Vf}.k Ni /1M l} h1.
/IM,'ers_.
K k.-,N.G.. , _'.-
- y K >1 A> 1w N' N V'AY^ # 'i " \'"' '
P 900 ^'i 1.3 1.4 1.5 1.6 1.7 1.s Entropv
r T A BLI D 1.i' Properises of Dr.s Satur.iiest Sicem +
Prenurc e, Sre nt., .:. E nin sip, g ,,,,,,
press ,
em 5* ' 5*' 58: Sai sai s.
~
.I 1.eud .sco, i.eva Eur ..p ,, g,q,4 E ar ,p, r 8 ', ', A s
A m 4, s, s, e, 1.0 101.74 0.01614 3336 69 70 1036.3 1106 0 0 1326 1.8456 1.97t2 20 126.0d 0.01623 173 73 93 99 1022.2 1116.2 0.1749 1.7451 1.9200 3.0 141 db 0 01610 lib 78 109 37 1013.2 1922 6 0.2006 1.6855 1.8863 40 152 97 0.01636 90 63 120 ko 100t> d 1127.3 0.2196 1.6427 1.8625 5.0 162.24 0.01640 73.52 130 13 1001.0 1131.1 0.2347 2.6094 1.8441 60 170.06 0 01645 61.98 137.% 996.2 1134 2 0.2472 1.5820 7.0 1.8292 176.85 0 01649 53 64 144 76 992.1 I I%.9 0.2581 1.5586 8.0 1.8167 182.86 0.01653 47.34 150 79 985.5 l139.3 0.2674 1.5363 1.8057 9.0 185.2b 0 01656 4: 40 156 22 965.2 1141 4 0.2759 1.5203 l.7962 10 193.21 0.01659 3842 161.17 982.1 1843.3 0.2R15 1.5041 1.7876 14.696 212.00 0.01672 26.80 180 07 970.3 1150 4 0.3120 1.4446 1.7566 15 213.03 001672 26 29 Illi 11 %97 1150 5 0.31M l.4415 1.7549 20 227.% 0 01653 20 089 1% 16 9601 1156.3 0.3356 1.3962 1.7319 25 240.07 0 01e92 16.301 20> 42 9521 1.360t, 1160 6 0 3533 1.7139 30 250 33 0.01701 13.746 216 62 945.3 1164 1 0 3680 1.3313 1.6993 35 259.2B 0.01706 11.89b 227.91 939.2 1167.1 0.3807 1.3063 1.6870 40 267.25 0.01715 10 496 236 03 933.7 1169.7 0.3919 1.2844 1.6763 45 274.44 0.01721 9.401 243.36 928.6 1172.0 0.4019 1.2650 1.6669 50 281.01 0.01727 8.515 250.09 924 0 1174.1 0 4110 1.2474 I.6585 55 287.07 0.01732 7.787 256.30 919.6 1175.9 0.4193 1.2316 1.650s 60 29271 0 01735 7.175 262 09 915.5 1177.6 0 4270 1.2168 1.6436 65 297.97 0.01743 6.655 267.50 911.6 1179.1 0.4342 1.2032 1.6374 70 302.92 0.01748 6.206 272.61 907.9 IISO 6 0.4409 1.1906 1.6315 75 307.60 0.01753 5.816 277.43 904.5 1881.9 0 4472 1.1787 1.6259 30 312.03 0.01757 5.472 282.02 901.1 1183.1 0 4531 1.1676 1.6207 85 316.25 0.01761 5.168 286.39 897.8 1184 2 0 4587 1.1571 1.6158 90 320.27 0.01766 4 896 290.56 894 7 1885.3 0 4641 1.1471 1.6112 95 324 12 0.01770 4.652 294.56 891.7 l186.2 0.4692 1.1376 1.606h 100 327.81 0.01774 4.432 298 40 888.8 1887.2 0 4740 1.1286 1.6026 110 334 77 0.01782 4.049 305.66 883.2 1188.9 0 4832 1.1817 1.5946
r e .
TABLE D la Properte of Dry Saturaled Sicam Icontinued, Pressure Specific volume I.fittstr% t nittp g
ltfe r .
'"" 9 5.i sai sei Sa' sai 5.c
- 1.go.d sence i.e ved I'*P sarc. leav.d liar ,,pn
- , he he he * *n **
! * *r 3.72b 312 44 877.9 1190 4 0 4916 1.096: 1.5876 120 341.25 0 01789 347.32 001796 3 455 318.81 872.9 1191.7 0 4995 1.0617 1.5812 130 140 353.02 0.0180 3.220 324.82 866.2 1193 0 0.5069 1.068: 1.5751 0 01809 3.015 33051 863 6 1194 1 0 5138 1.0556 1.5694 150 35> 42 36353 0 01815 2 834 335.93 859.2 1895 1 0 5204 1.0436 1.5640 160 170 3t4 41 0.018:2 2 675 341.09 BM9 I1% 0 0.5266 1.0324 1.5590 373 06 0.Olb27 2'53: 346 0.1 850 8 11 % .9 0.5325 1.0217 1.554 180 377.51 0.01833 2 404 350.79 8468 1891 6 0.5361 1.0116 1.5497 190 381.79 0 01839 2.28h 355.% 843.0 1896 4 0 5435 1.0018 1.5453 200 250 400.95 0 01865 1.8438 376 00 825.1 1201.1 0.% 75 0.958B 1.5263 300 417.33 0 01890 1.5433 393 84 809 0 1202 8 0.5879 0 9225 l.5104 431.72 0 01913 1.3260 409 69 794.2 1203.9 0 6056 0 8910 1.4966 350 400 444.59 0 0193 1.1613 424 0 780.5 1204.5 0.6214 0.8630 1.4844 4 50 456 28 0.0195 l.0320 437.2 767.4 1204 6 0.63 % 0.8378 1.4734 500 467.01 0 0197 0 9276 449.4 755 0 1204 4 0 6487 08147 1.4634 550 476 94 0 0199 0 8424 460.8 7431 1203.9 0 6606 0 7934 1.4542 600 466.21 0 0201 0.7696 471 6 731 6 1203.2 0 6720 0 7734 1.4454 650 494.90 0.020.1 0.7063 481.8 720.5 1200.3 0.6826 0 7546 1.4374 700 503 10 0 0205 0.6554 491.5 7097 1201.2 0.69:5 0.7371 1.4296 750 510.86 0.0207 0.609 500.6 699.2 I200.0 0 7019 0.7204 1.4223 800 $18.23 0.0209 0. % 87 509.7 688.9 1198 6 0.7108 0.7045 1.4153 850 525.26 0.0210 0.5327 518.3 678.8 1197.1 0.7194 0.6891 1.4085 900 531.96 0.0212 0.5006 526.6 6688 1895 4 0.7275 0.6744 1.4020 950 536 43 0.0214 0 47I7 534 6 659.I 1193.7 0.7355 0 6602 1.3957 1000 $44 61 0.0216 0.44 % 542.4 649.4 1891.8 0.1430 0.6467 1.3897 1100 5 %.31 0.0220 0.4001 557.4 630 4 1887.7 0.1575 0.6205 1.3780 1200 %7.22 0.0223 0.3619 571.7 611.7 1183.4 0.7711 0.59 % 1.3667 1300 577 46 0 0227 0.3293 585.4 593.2 1178.6 0.7840 0.5719 I.3559 1400 587.10 0 0231 0.3012 598.7 574 7 1173 4 0.7963 0 5491 1.3454 1500 596.23 0,0235 0 2765 611.6 5%.3 1167.9 0 8082 0.5269 1.3351 2000 635 82 0.0257 0.1878 671.7 463 4 1135.1 0.8619 0.4230 1.2849 2500 668.13 0.0287 0.1307 730.6 360.5 1091.1 0.9126 0.3197 1.2322 l 3000 695.36 0.0346 0.0858 802.5 217.8 1020.3 0.9731 0.1885 1.1615 )
3206.2 705.40 0.0$03 0.0503 902.7 0 902.7 1.0580 0 1.0580 ,
l l
l l
l
\
o .
TABLE D Ib Properties of Dr) Saturated Steam (contmurds
- Temperature specar solvene Embeirs Ermors 7emr.
^*
5.i
.= P'
- sc sr se Eist
$si
,,po, s o-
, e,,,g Isar ,, p,,
P I,quie s a no- liewee r 's h ha h s
- 'n *s e *: o 0 00 10758 1075.8 0.0000 2.1877 2.1877 32 0.08854 0.0160: 3306 3.02 1074 1 1077.1 0.0061 2.1709 2.1770 35 0.09995 0 01602 2947 0 01602 2444 8 05 1071.3 1079.3 0.0162 2 1435 2 1597 40 0 12.170 2.1167 2.1429 2036 4 13 06 106b 4 1061.5 0 0262 45 0 14752 0 01602 2.1264 17032 16.07 1065 6 1063 7 0 0361 2 090) 50 0.1411 0 01603 1059.9 1088 0 0.0555 2.0393 2 0946 60 0 2563 0 016068 1206.7 28 06 1054 3 1092.3 0 0745 1.990: 2.0647 70 0 3631 0.0160o 867.9 38 04 48.0: 1046 6 1096.6 0 0932 1.94:6 2.0360 30 0.5069 0.0160b 633.1 57.99 1042.9 1100.9 0.1115 I.8972 2.0087 90 0.6982 0.01610 468 0 1037.2 1805.2 0.1295 1.8531 1.9826 100 0.9492 0.01613 350.4 67.97 10316 1109.5 0.1417 1.8106 1.9577 110 1.27 4 0 01617 265 4 77.94 87.92 10:5.6 1113.7 0.1645 1.7694 I.9339 120 1.6924 0.01620 203.27 97.90 1020.0 1117.9 0.1816 1.7296 1.9112 130 2.22:5 0.01625 157.34 1014.1 1122.0 0.1964 1.6910 1.8894 140 2.8886 0 01629 123.01 107.89 1005.2 1126.1 0.2149 1.6537 1.8685 150 3.116 0 01634 97.07 117.89 127.89 1002.3 1130.2 0.2311 1.6174 1.8485 160 4 741 0 01639 77.29 996.3 1134.2 0.2472 1.$5:2 1.8293 170 5.99: 0 01645 62.0e 137.90 147.92 990.2 1138.1 0.2630 1.5480 1.8109 180 7.510 0.0165I 50.23 40 96 157.95 964.1 1142.0 0.2785 1.5147 l.7932 190 9.339 0 01657 167.99 977.9 1145.9 0.2936 1.4824 1.7762 200 11.526 0.01663 33.64 178.05 971.6 1149.7 0.3090 1.4508 1.7598 210 14.123 0.01670 27.82 26.80 180.07 970.3 II50 4 0.3120 1.4446 1.7566 212 146% 0.01672 23.15 188 13 965.2 1153 4 0.3239 1.4201 1.7440 220 17.186 0 01677 19b.23 95t.8 1157.0 0.3387 1.3901 1.7285 230 20.780 0.01664 19 382 206.34 952.2 1160.5 0.3531 1.3609 1.7140 240 24.% 9 0.01692 16.323 216.48 945.5 1164.0 0.3675 l.3323 l.6998 250 29.825 0.01700 13.821 938.7 1167.3 0.3817 1.3043 1.6860 260 35.429 0.01709 11.763 22P .64 931.8 1170.6 0.3958 1.2769 1.6727 270 41.858 0.01717 10.061 238.84 924.7 1173.8 0.4096 1.2501 f.6597 280 49.203 0.01726 8.645 249.06 259.31 917.5 1176.8 0.4234 1.2238 1.6472 290 57.556 0.01735 7.461 910.1 1179.7 0.4369 1.1980 1.6350 300 67.013 0.01745 6.466 269.59 902.6 1182.5 0.4504 1.1727 1.6231 310 77.68 0.01755 5.626 279.92 4.914 290.28 894.9 1185.2 0.4637 1.1478 1.6115 320 39.66 0.01765 1.6002 330 103 06 0.01776 4.307 300.68 887.0 lI87.7 0 4769 1.1233 340 118.01 0.01787 3.788 311.13 879.0 1190.1 0 4900 1.099: 1.5891
r TABLE D Ib Properties of Dr.s Saturated Steam tennimurd-IemperJ1urc
$ recd tclume L niNir3 k mors 7emp.
- F Sai $at Sai Sai $si $ai II liqu4 II *aror lequid waror liqud toror e r *, ', A, A. 4, 8, 8 8, 350 134 63 0 01799 3.34 321 6.2 870 7 1192 .1 0.5029 1.0754 1.5783 360 153 04 0 01611 2 957 33: 16 85: 2 1194 4 0 515b 10519 I.5677 370 173.37 001823 2.625 34: 79 853 5 119t, 3 0 5:bo 10 b? 1.5573 380 195.77 001636 2 335 353 45 8446 1l9b 1 0.5413 1.0059 1.5471 390 220.37 0 0lb50 2.0836 364.17 835 4 1199 6 0.5539 0.9832 1.5371 400 247.31 0.01864 1.8633 374 97 8260 1201.0 0.5664 0.9606 1.5272 410 276 75 00187b I.6700 385 83 816 3 1202.1 0 5788 0 9366 1.5174 420 306 83 0 01894 1.5000 3 % 77 806 3 12031 0.5912 0.9166 1.5076 430 343.72 0.01910 1.3499 407.7f 796 0 1203 6 0.6035 0.8947 1.4982 440 381.59 0.01926 1.2171 418 90 7854 1204.3 0.6156 0.8730 1.4887 450 422 6 0.0194 1.0993 430.1 774.5 1204 6 0.6 00 01513 1.4793 460 466.9 0.01 % 09944 44I 4 763 2 1204 6 0 6402 08296 1.4700 470 Sid 1 0 0198 0 9009 45 6 751.5 12043 0.65:3 0 8013 14MW 480 5661 0 0200 0 817 464 4 739 4 1203 7 0 6645 07b66 14513 490 621.4 0 020 0.7423 476 0 7266 120 b 0.6766 0 7653 1.4419 500 680.6 0 0204 0 6749 487 6 713 9 12017 06hF' O7436 1.43:5 520 812.4 0 0209 0.5594 SI 1.9 6864 l196 2 0 7130 0.7006 1.4136 540 962.5 0.0215 0.4649 $36 6 656 6 1193.2 0.7374 0.6566 1.3942 560 1133.1 0 0:21 0.3868 562 2 624.2 lib 6 4 0.7621 0 6121 1.3742 "
580 13:5.8 0 0:26 0.3217 585.9 588 4 1177.3 0.787 0.5659 1.353:
600 1542 9 0.0 36 0.2666 610.0 546.5 1165.5 0.8131 0.5176 1.3307 620 1786.6 0.0247 0.2201 646.7 503 6 I150.3 0.8398 04664 1.1062 640 2059.7 0 0260 0.1798 678.6 452 0 1130.5 0.8679 0.4110 1.2789 660 2365.4 0.0278 0.1442 714.2 390.2 1104 4 0 8987 0.3485 1.2472 680 27081 0 0305 0.1115 757.3 309.9 1067.2 0.9351 0.2719 1.2071 700 3093 7 0 0369 0 0761 823.3 172.1 995 4 0.9905 0.1484 1.1389 705 4 3206 2 0 0503 0 0503 902.7 0 902.7 1.0580 0 1.0580 I
Proportses of Superheeled Sisam*
Ahn press . Temperosers. 4 ts. M .g i 300 3ou doo seu em m sou sou loco lico 1300 isov
,, M26 452 3 512 0 571.6 631.2 690 8 750 4 809 9 869.5 929 I 988 7 1307.8 1 &. 1830 4 8195 8 1241.7 1288.3 1335 7 1383 8 1432.8 1442 7 1533.5 1585.2 1637.7 17457 CII.74) s...... 2D512 2.1153 2.l730 2.2233 2.2702 2.3137 2.3542 2.3923 2 42:3 2 4625 2.4952 2.5566
- v. 78 16 90.25 102.26 114.22 126 16 138 10 130 03 161.95 173 87 185.79 197.71 221A 5 & .. . 1848 8 1895.0 1241.2 1288.0 1335 4 1383 6 1432 7 1452 6 1533 4 1585 1 1637.7 , 17457 .
(162.24) a. . I.8718 1.9370 1.9942 2.04 % 2 0927 2. t hi 2.1%7 2.214n 2.2509 2.2851 2.3178 2.3792
,. 38 85 45.00 $1.04 57.05 63 03 69 01 74 9a no 95 M6 92 9288 98 84 110 77 10 A. 1846 6 l 193.9 1240 6 1287.5 13351 1383 4 1432.5 14a2 4 531.1 2 15:5 0 1637.6 1745 6 (193.21) s. 1.7927 l.8595 8.9672 1. % 89 2 0160 2 0596 2 1002 213m t 2744 2 206h 2.2413 2.3028
,. 30.53 34 68 36 76 42 86 46 94 5100 5507 Sv i3 6319 67.25 75 37 14 696 A. 1192.6 1239 9 12871 1334 b 136)2 1432 3 1462 3 153.4 5 15k4 > 1637.5 1745 5 (212DD) s. 1.8160 1.8743 1.9261 1.9734 2 0170 2 0576 2 0956 2 1319 2 1662 2 1989 2.2603
,, 22.36 25.43 28 46 31.47 34 47 37.# 40 45 43 44 46 42 49 41 55.37 JO A. 1891.6 1239.2 1286.6 1334 4 1382 9 14321 1482.1 1533 0 1584 7 1637.4 1745 4 (227.96) a. l.7808 1.8396 1.8918 8.9392 1.9629 2.0235 2.061s 2.0978 2.1321 2.1648 2.2263
- e. 11.040 12 628 14.168 15 688 17.198 18 702 20.20 21.70 23 2n 24 69 27.68 40 A. 18868 12 %.5 12848 13331 1381.9 1431.3 1481.4 1532 4 15b41 1637.0 1745I (267.25) .S . l.6994 I.% 08 I8140 1.8619 f.9056 1.9467 1.9850 2 0212 2 0m 2.086) 2.1496
- y. 7.259 8.357 9 403 10 427 11 441 12 449 13452 14454 15 du 16 451 18 446 60 A. 1181.6 1233.6 1283.0 1331.8 1380 9 1430 5 1480 8 153'.9 15xi m 16 %.6 1744 8 (292.71) s. . I.6492 1.7135 8.7676 8.8162 1.8605 1.9015 1.9400 1.9762 2.010b 2 0434 2.1049
- e. .. 6.220 7.020 7.797 8.%2 9.322 10.077 10 830 11 Sn2 12.332 13.830 80 A. . 1230.7 1281.1 1330.5 1379.9 1429.7 1480.1 1531.3 15x3 4 16M.2 1744.5 (312D3) s. . 1.6791 l.7346 1.78M 1.8281 l.8694 1.9079 1.9442 1.97M7 2.0115 2D731
,. 4.937 5.589 6.218 6.835 7.446 8.052 8.6% 9.259 9.860 11.080 100 A. . 1227.6 1279.1 1329.1 1378.9 1428.9 1479.5 1530.8 1542.9 1635.7 l%4.2 (327.81) s . . l.6518 1.7085 1.7581 1.8029 1.8443 1.8829 8.9193 1.9538 1.9867 2 Des 4
,. 4.081 4.6% 5.165 5.683 5.195 6.702 7.207 7.710 8.212 9.214 130 A. . .. 1214 4 1277.2 1327.7 1377.8 1428 1 1478 8 1530.2 1582 4 1635.3 1743 9 04n 251 s. y 1.6287 14469 1.1310 , l.7822 1.8237 2.8625 l.8990 1.9335 1.9664 2.0241
{. ... .
{. . g
- e. .
3 48 3.9 54 4 413 4.861 5.301 5 738 6.172 140 A. 1221.1 8275.2 1326 4-6 604 7.035 7sv 13 %.8 1427.3 1478.2 1529.7 1581.9 (353 02) s. l.6067 1.6683 1.7190 I.7645 1634.9 1741 %
1.8063 1.8451 1.8817 1.9163 1.9493 2.0110 O e. 3.008 3 443 3 849 4.244 4.631 5.015 5.3%
160 A. 1217.6 12731 1325 0 5775 6 152 6.90t 1375 7 1426 4 1477.5 1529.1 1561 4 (M3.531 s. l.590b l.6519 1.7033 1.7491 1634 5 1743.2 1.7911 I.8301 1.8667 1.9014 I.9344 1.9962
- e. 2.649 3.044 3.411 3.764 4.110 4.452 4.792 180 A. 1214.0 1271.0 1323.5 5.129 5 466 6.136 1314 7 1425.6 1476.8 1528 6 (373.06) s. 1.5745 1581.0 1634.1 1742.9 1.6373 1.6894 1.7355 1.7776 1.8167 1.8534 1.8882 I.9212 1.9831
- v. 2.361 2.726 3 060 3.380 3.693 4 002 4.309 Xio A. 1210 3 1268 9 1322.I 4 613 4.917 5.52i 1373 6 1424 6 1476.2 15280 15'O 5 (121.79) s. l.5594 1633 7 1742.6 1.6240 1.6767 1.7232 1.7655 I.8048 1.8415 1.8763 I.9094 1.9713
- e. 2.125 2.465 2.772 ]
3.066 3.352 3.634 3.913 4 #7 220 A. 1206.5 12667 4.191 5.017 '
1320.7 1372 6 1424 0 1475 5 1527.5 '
(389-86) s. 1580 0 1633.3 1742.3 l.5453 l.6117 1 6652 1.7120 1.7545 1.7939 1.8308 1.8656 1.8987 I.9607 l.9276 2 247 2.533 2 804 3Op 240 A. 3 327 3.5bi 3 839 4 093 4 597 !
1202.5 .264 5 1319 2 1371.5 1423 2 1474b 1526 9 1579 6 1632.9 (397.37) s. 1.5319 I.6003 1.6546 1.7017 1 7444 17839 1742 0 18209 I8558 1.88h9 1.9510
.. 2.063 2.330 2 562 2827 3.067 3.305 260 A. 3.54 1 3.776 4.242
. .. 1262.3 1317.7 1370 4 1422.3 1474.2 1526 3 (404.42) s. 1579.1 1632.5 1741.7 l.5897 l.6447 1.6922 1.7352 1.7748 1.8618 1.8467 1.8799 1.9420 l.9047 2.1 % 2.392 2.621 2.845 3.066 280 A. .
1260 0 1316.2 1%94 3.286 3.504 3.938 1421.5 14735 1525 8 1576 6 1632.1 (411D5) s. .
. .. 1.5796 1.6354 1.6834 1.7265 1741 4 1.%62 1.8033 1.8383 1.8716 1.9337
- e. . ... l.% 75 2.005 2.227 2.442 2.652 2 859 3.065 300 A. . . 1260 0 1316.2 IM83-3.269 3.674 (417.33) s, 1420 6 1472.8 1525.2 1578 1 1631.7 1741.0 l.5701 1.6268 1.6751 1.7184 1.7582 1.7954 1.8305 1.8638 f.9260
- e. . . l.4923 1.7036 1.8980 2 084 2.266 2 445 350 A. . .
1251.5 1310.9 2 622 2.798 3l47 ,
1365.5 1418.5 1471.1 1523.8 (431.72) s. .
1.5481 1.6070 1577.0 1630.7 l'40.3 l 1.6%3 1.7002 1.7403 1.7777 1.8130 1.8463
,. 1.9086 l
. . . . 1.2851 1.4 770 1.6508 f.8161 1.9767 l 400 A. 2.134 2 290 2 445 2 751 1 (444.59; s .
.. . . . . . . . . 1245.1 1306 9 IM27 1416 4 l#94 1522 4 1575.8 1629 6 1739.5
. . . . .. l.5281 1.5894 1.6M4 1.6842 l 1.7247 1.% 23 1.7977 1.83ll 1.8916 '
l
l j
i l
1 (Units Are Arbitrary)
.h N -
Q 8>
h* Y 5
15 - o %
J o/
10 4 bP" (o rV C 6
x 8 e a , , ,
1 2 3 4 5 6 7 g Pump Speed (Units Are Arbitrary) f
\
Tigure 6,2-3. Pump Laws I
= *
?
- Page 154 - ,
SURFACE UTILIZATION Vs FLOW 100 80 l
\\ \\ ' '
\ \
3 ,, Su\.rheat \ \ d i
i '/
s \ \ -
W
.0
,, \
X N
WV .
r
- r 4,....
Bolling 0
0 to 40 60 80 100 Full Lead. %
FIGURE 43
10 . - l POWE R. %
1 50 I 1 30 60 90 TIME (HR) 4 150 - 150 -
100 - x.100 -
1 Conc )
k 1
- 50 - l (enc. 50 l l
l 1 1 I I I I l 30 60 90 30 60 90 TIME (HR) TIME (HR) 150 -
l 150 -
Xe 100 -
100 -
o hc.
t
~
(o n c. 50 -
I ' I i i I 30 60 90 30 60 90 TIME (HR)
T M (H N C*
J n.
-WORT. SHEET 11- ENCLOSURI 2 (Page 1 of 2)
IST1 MATED CRITICAL. BORON CONCEhTRATION 532'F , 01 FF No Renon, No Cont rol Rode ,
REFERENCE CONDITIONS:
Equilibrium Samarius
- 1. Fuel Resetivity 200 rrru asfa
- a. Core Burnup --
- b. Road Curve 3.1 of OP-103, Plant Curve Book.
- 2. Eenon Resetivity (Use Step 2.1 or 2.2) 2.1 Value calculated by SA10N I (submit printout).
( I ak/h) = 1 ak/k on i
. 2.2 s. Last power level was 100 1 FP for 80khrs.
j b. Time Shutdown 24 hre.
i c. If time at last power level was < 40 hre. and SAKON is unavailable, consult with Reactor Specialist.
2 f
( I ak/h) = 1 ak/k I 3. Samarius Reactivity Buildup After Shutdown 1
Value calculated by SAXON 1 (submit printout) I ak/k 3.1
- 4. Reactivity Effect From Temperature
- a. Average RC Temperature 8 9 8 #F
- b. Reference temperature is 5320T.
l
- c. Temperature coef ficient at ppm 3 is obtained from Curve 3.6 of OP-103, Plant Curve Book, to be z 10-21 ok/k/0F.
- d. Reactivity = (T(ave) - 532) (Temp. Coef f. ]
- e. Reactivity = ( -
)( z 10-21 ak/k/oF)= 1 Ak/k
- 5. Rasetivity of Control tods at Desired Insertion Groupe 1-4 at 100 % WD ,
l Group 5 at Joe 1 WD i Croup 6 at 100 1 WD Croup 7 at B0 1 WD Regulating Group Worth I ak/k I ak/k
+
Group 8 at 90 1 UD Group 8 Worth i j )
l Calculated By Date l
i
\
Date 11/16/82 Page 18 0P-210 Rev. 16
FIGURE 2.1-2 asAc70R 0D31 SAFETY LDtIT
. 120 E
112 = (33.60. 112) 44.80. 112) - . , 110 (Re.g h h) Q
(-47.87. y ,
- - 100 DI39*97' *I3) 99.93) (.44.80, 89.70)
(33.60. 89.70) ^
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l
! d# REV 00 Date 06-03-83 AP-380 ESSA l FOLLOW.WP (Cent'd)
ACTIONS - . DETAILS ]
NOTE
) 14. IF RCPs are available. i 1
THEN ensure: RCPs are available when the i i
following criteria are met:
o Seal injection
- e Pump start Permissive e Seal return e Power available e SW cooling AND:
- a. 11 OTSGs available.
THEN start 1 RCP in each loop NOTE OR start 2 RCPs in one
- d Tiop RCP-1B is preferred.
SR.
- b. IF OTSGs NOT available.
![ RCPs NOT available.
THEN start one RCP. THEN refer to AP-530, Natural ETeculation.
i l
l Page 9 of 25 ESSA AP-380 J
/ ,
(~$ L, 3 l
- r. .
O ESSA REV 00 Date 06-03-83 AP-380 racL0sunt 1
'RCP CURVES 1000 l i I I i i i i t 900 -
800 -
- 700 -
$2 iRCP E 600 -
O. . RATION -
m O E500 a.
o 400 -
e 300 -
200- 2 RCP .J OPERATION 10 0 -
O ! I I i i i i i i O .
100 200 300 460 500 ..
RC TEMP,TC( F)
AP-380 Page 25 of 25 ESSA O ,
/' .
i REV 02 Date 04-12-84 EP-290 ICC
^
l r ~
E0LLOW-UP.(Cont'd
^ ------ ---
' - - - ^
1.8 Refer to Figure 1.
o IF i n Region 2 IIIEN go to Step 1.9 o TT~Tn Region 3 TREN go to Section 2.0 M AD > 1400')
o IF i n Region 4 HEN go to Section 3.0 t' CLAD > 1800*) '
- - - - - - ^-
m Figure _1 CORE EXIT FLUID TEMPERATURE FOR INADEQUATE CORE COOLING 2GCC , , , , , , . .
240C ~
SAT LINE ~
220C REGCN l ~
200C - Tyg >i400
~
1800 - REGCN IGCC -
$ I400 k I200 -
3 M coo .
GOC -
~
G00 -
TCLAO >i800 400 - -
2M 400 600 $O0 , IOc0 1200 CCRE >~RNCCOL9LE FW WI
- ___J -- -
r
- ' WsAW & w*tA.
ANSWERS SECTION 1 1.1 d. Ref: NETRO 10.2-2 (1.0) 1.2 b. Ref: NETRO 11.4-3 (1.0) 1.3 b. Ref: Duke Power Company, FNRE; pp. 126-128 (1.0) 1.4 d. Ref: CR3'HTFF, pp. 158 and 159 ( 1.0)
- 1.5 b. Ref: CR3 HTFF pp. 148-156 (1.0) 1.6 a. Ref: 1. Duke Power Company, FNRE; pp. 115-120 (1.0)
- 2. NETRO, 12.1-4 1.7 b. Ref: 1. OP-210, Rev. 16, p.8 (1.0)
- 2. NUS, NETRO, Unit 6
- 3. Westinghouse Reactor Physics, Sect. 3 & 5 1.8 a. Ref: NETRO, p. 10.3-2 (1,0) 1.9 'd. Ref: NETPP,' p. 6.2-5 (1.0) 1.10 c. Ref: NETPP, p. 6.4-5 (1.0) i 1.11 b. Ref: CR3 HTFF p. 151 (1.0) I l
l i
1.12 b. Ref: Steam tables or Mollier diagram (1.0) 1
)
2 1.13 c. Ref: 1. Westinghouse NTO, p. I-5.77 (1.0)
- 2. NETRO, 10.5-2
- 3. Duke Power Company, FNRE; p. 169 1.14 c. Ref: NETRO, p. 10.4-2 (1.0) 1.15 a. Ref: 1. STM-6-17, 18 (1.0) 1.16 a. More Inserted (50% equil Xe; +p) (2.0)
- b. More Inserted (Xe free; + p)
- c. More inserted (535 - 532 F)
- d. More Inserted (difference =.35%, Curve 3.9)
Ref: OP-210 and OP-103 1.17 c. Ref: 1. GP, HTT and FFF, IIB 2, p. 182 (1.0)
- 2. CR, HTT, Section 1 pp. 71, 157 1.18 b. Ref: TS p. B 3/4 1-1 (1.0) 1.19 d.+ L Ref: TS p. 3/4 2-12 (1.0)
TS p . B 2. - S' 1.20 d. Ref: STS B 6-4 (1.0) 1.21 b Ref: NETPP pp. 6.5-1 to 6.5-3 (1.0) 1.22 c. Ref: CR3 HTFF, 4th from last page (1.0)
r 3
1.23 a. axial power imbalance (2.0)
- b. reactor power, % thermal power
- c. acceptable 3f4Ipumpoperation ,
- d. acceptable 4 pump operation Ref: TS Figure 3.2.2.
f f
j.
l t
l i
i i
r 4
ANSWERS SECTION 2 2.1 b. Ref: ANO-91, p. 6, Rev. 0 (1.0) 2.2 d. Ref: AND-102, pp. 1, 11, and 14 (1.0) 2.3 b. HP flash tank is correct, MSRLP flash tank is wrong (1.0)
(p. 15) (a); 1A/B, 2A/B heaters do not have non-return valves, pp. 19 & 20 (c); only on 1A/B, 2A/B heaters, pp. 18 & 19 (d).
Ref: NAO-99, pp. 15-20 2.4 b. Ref: STM 25-3 (1.0) 2.5 b. Ref: STM2-77 (1.0) c,.
- 2. 6 ,j(I Ref. STM2-11 (1.0) 2.7 a. Ref: STM4-2 (1.0) 2.8 d. Caution - N2 heater should not remain energized for (1.0) extended period with no N2 flow (a); waste disposal system CFV-ISF,16F (b); aux bldg sump (c).
Ref: OP-401 p. 7
- v. ,
a e 5
2.9 c. Ref: .STM-12-9 (1.0) 2.10 c. Ref: STM 28-4 (1.0) 2.11 c. Ref: STM 405 p. 2,6, 7 (1.0)
NOTE: (c) is a criterion test item; no, fully redundant (a);
raises pH to alkaline (b); DHCCS p. 11 (d).
o1 2.12 1. Upper brustbearing) Cooler (2.0)
- 2. Lowe(Guide ring ooler
- 3. Motor air cooler
- 4. Seal Area Cooler Ref: STM-23-7 and 8 2.13 a. Ref: STM 22-1 and 44 (1.0) 2.14 a. Ref: STM 17-10 and 12 (1.0) 2.15 d. Ref: STM 17-5 (1.0) 2.16 b. Ref: STM 10-4 and 5 (1.0) 2.17 b. Ref: STM 1-17 (1.0) 2.18 c. Ref: PASS lesson plan R0-105 p. 8 (1.0)
r 'l t
6 2.19 b. (1.0)
- a. 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> @ nameplate rating
- c. 1-AC, J-DC
- 2. STM 10-8 & 12.
2.20 a. A-1, B-2 (0.5)
- b. A-2 (0.25)
- c. B-1 & A-2 (0.5)
- d. B-1 (0.25)
- e. A-1 & B-2 (0.5)
Ref: CR Main Steam Handout
....- . . . 4 .. . . . . ,. , . ... .
2.21 c. Ref: OP-605, p. 5 and 6, Rev. 28 (1.0)
+b 2.22 c. Ref: STM-38-7 (1.0) 2.23 a. 4
- b. 3
- c. 5
- d. 1 Ref: STM 15-17
f 7
2.24 1. Open DHV-11 and 12 (LPI to HPI cross connects) (0.33 each)
- 2. Close MUV-58 & 73 (BWST Suction valves)
- 3. Open DHV-42 and 43 (RB fump suction valves)
- 4. Close (BSV-36 & 37) (NA0H tank outlet valves) - (Not required)
Ref: STM 4-9 thru 12 h -
1 4
__ l STe p M.7 Op 1)t4 V - 34 4 %~
g Op DH V- ( \ + \'-
Chu_ Mu u- W+ r 3 sqf 2 5. @'^ 4 2. + 'l 3 C W 34+SC
r 8
3.1 c. Ref: OP 504, p. 3, Rev. 7 (1.0) 3.2 b. Ref: STM 13-2 (1.0) 3.3. a. Ref: STM 12-11 (1.0)
STM 12-13 3.4 a. Ref: STM 20-2, 3 (1.0) bdd 3 . 5 .d - Ref: OP-504, p. 8, Rev. 7 (1.0)
STM 27-56
'A' 'B' 3.6 (2.0)
- a. Main FW Block Valve ( FWV-30 FWV-29) (0.25 ea.)
. - Lo-Load 9 -" (FWV -
FWV-32)
Startup " "
(FWV-36 FWV-33)
Emergency " ( FWV-35 FWV-34)
Emergency Bypass Valve ( FWV-162 FWV-161)
MFWP Suction Valve ( FWV-14 FWV-15)
FW Crosstie (--------FWV-28--------)
MSIVs (MSV-411,412 MSV-413, 414)
- b. 1. Affected OTSGs pressure has recovered to >725 psig (1.0)
- 2. Rupture matrix is bypassed Ref: CR SLRM handout
I 9 .
3.7 b.
Ref: Power System Operation (1.0)
R. H. Miller, p. 22-24 3.8 a. Ref: STM 6-4 (1.0) 3.9 b. Ref: RPS Handout, p. 21 (1.0)
NOTE: State lamp - auto reset deadband set for maximum 3.10 Particulate and iodine are looking at buildup on filters. (1,0)
May signify filters have to be changed.
Ref: STM 43-12 to 16 3.11 d. Ref: STM 6-24
~
3.12 b. Ref: STM 504-93 3.13 c. Ref: STM 43-9 Ref: STM 15-10 3.14,me'd CL di 3'.15 a. Ref: STM 16-10 3.16 d. Ref: RPS Handout, pp. 29, 33, 34
r 10
^
3.17 b Ref: STM 28-18 & 19 (1.0) 1 12 d if- ST" 10-47 1 00 ' (1.0) 3.19 a Ref: STM 2-121 (1.0) 3.20 b Ref: STM 12-14 (1.0) 3.21 d Ref: STM 17-19 (1.0) 3.22 a. 1. 270 110 (1.0)
- 2. 100 Ito (0.2 each)
- 3. 170 $to . .
- 4. 50 8
- 5. 10 o
- b. 1. 'n; Trze Ld c1A. b y Te, (1.0)
- 2. DH-Hx 4eSe4. OuJtt.t Temp . (0.5 each) o
- 3. N w c,w 12m ge Tc. 2 S 10 1re m Ref: a. OP-209, p. 2, Rev. 48
- b. OP-209, p. 11, Rev. 48
r I
11 4.1 a. NONE (AP-241) (2.5)
- b. 1, 2, 3, 7, 8 (AP-242) (0.5 each) f
- c. 3 (AP-243)
- d. 2 (AP-244)
- e. 4, 5, 6, 7, 9 (AP-245) l D 4.2 1. Notify AB operator to ensure S$V-90 closed (0.25)
D
- 2. NotifyTBoperatortostopS$P-7 J (0.25)
Ref: AP-277, pg. 2, Rev. 00 l
4.3 a Ref: AP-320, p. 2, Rev. 00 (1.0) 4.4 d Ref: AP-360, p. 1, Rev. 00 (1.0) 4.5 1. . Bypass ES Actuation .
(.33 each)
- 2. Return ES equipment to STBY status
- 3. Go to VP-580 Ref: AP-380, p. 3, Rev. 01 I
l L
12 4.6 1. Ensure both MFPs tripped (2.0)
- 2. Ensure closed: MBVs LLBVs SUBVs
- 3. Ensure both EFWPs start
- 4. Ensure emergency feedwater block valves open
- 5. Close FWV-162 (A OTSG)
FWV-161 (B OTSG)
Ref: AP-450, Rev. 1 4.7 d Ref: OP-502, p. 4, Rev. 13 (1.0) 4.8 a Ref: OP-502, p. 8, Rev. 13 (1.0)
+b 4.9 c Ref: AP-380, p. 9, Rev. 00 (1.0) 4.10 b Ref: AP-501, p. 3 (1.0) 4.11 b Ref: OP-501, p. 2, Rev. 7 (1.0) l 4.12 d Ref: OP-403 (1.0) 4.13 c Ref: OP-204, p. 3 & 4, Rev. 36 (1.0)
oe. .
13 4.14 a Ref: EP-120, p. 2, Rev. 00 (1.0) 4.15 a Ref: OP-504, p. 15, Rev. 7 (1.0) 4.16 b Ref: OP-605, p. 3 & 4, Rev. 28 (1.0) 4.17 1. Ensure all feeder BKRs to affected bus are open. (1.0)
- 2. Close feeder BKR from Units 1 and 2 by holding in "Close" position for 10 seconds:
'A' bus BKR 3211
'B' bus BKR 3212' Ref: AP-770, p. 2, Rev. 00 4.18 b Ref: RP-101, p. 5, Rev. 19 (1,0) 4.19 b Ref: RP-101, p. 23, Rev. 19 (1.d)~
4.20 b Ref: 10CFR 20.101, p. 239 Rev. 1/1/85 (1.0) 4.21 a. False, AI-500, p. 9 (0. 5)
- b. False, AI-500, p. 9 (0. 7)
- c. False, OSIM, p. III-2
(,0,5 h
- d. True, OSIM, p. III-3 4.22 e Ref: EP-290, p. 7. Rev. 02
. mee UNITEJ STATES CUCLEAR CEGULATORY COMMISslON
- '~
RE060N 11 4
101 MARIETTA STREET.NR.
ATLANTA.0EORetA 30303
,,,,, ENCLOSURE 3 (2 of 2)
U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR REQUALIFICATION EXAMINATION Facility: Crystal River Reactor Type: B&W 177 Date Administered: July 9. 1985 Examiner: S. Lawyer Candidate:
INSTRUCTIONS TO CANDIDATE:
Use separate paper for answers. Write answers on one side only. Staple question sheet on top of the answer sheets. Points for each question are indicated in parenthesis after the question. The passing grade requires at least 70% in each categ and a final grade of at least 80%. Examination papers will be picked up four hours after the examination starts.
% of Category % of Candidate's Category Value Total Score Value Category 25 5. Theory of Nuclear Power Plant Operation. Fluids and Thermodynamics 25 6. Plant Systems: Design, Control & Instrumentation 25 7. Procedures-Normal. Abnormal.
Emergency Radiological Control 25 8. Administrative Procedures, Conditions and Limitations 100 TOTALS Final Grade %
All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature
a-5.0 THEORY OF NUCLEAR POWER PLANT OPERATION. THERMODYNAMICS. (25.0)
HEAT TRANSFER AND FLUID FLOW 5.1 During a reactor startup, power is being raised above the point of (1.0) adding heat (POAH). Which of the following statements is CORRECT?
(Assume a linear reactor power increase to about 3% power)
- a. Since header pressure is 885 psig, Tave will not rise above the corresponding saturation temperature of 532*F.
- b. Since the OTSGs are low level limited and header pressure is being maintained at 885 psig, Tave will rise and the steam temperature will tend to follow Th.
- c. With the header pressure being maintained at 885 psig, the OTSGs will remain at saturated conditions and no superheat will be added,
- d. Since the OTSGs are low level limited, the steam is superheated at zero power conditions and rises proportionally with power.
5.2 A general rule is often stated " doubling the count rate halver, the (1.0) margin to criticality." This is mathematically stated by the equation.
CR1 = 1-keff 2 TAY- 1-keff 1 Which one of the following statements is CORRECT concerning the above statement and equation?
- a. Both keffl and keff2 have to be less than 1.0.
- b. Equal changes in keff result in equal changes in subcritical multiplication level,
- c. The equation only approximates the instantaneous change in count rate; once equilibrium value is reached, the count rate will be higher.
- d. A second doubling of the count rate will result in the reactor becoming critical or supercritical.
e-2 5.3 OP-210, " Reactor Startup", requires that the critical rod position (1.0) be taken at 10 s amps on the intermediate range. If, during a xenon free reactor startup at MOL, the operator " overshot" 10 s amps and instead leveled off at 10 7 amps, which of the following statements is CORRECT?
- a. At 10 7 amps, there are little or no effects from nuclear heat but since the reactor is a decade higher in power, the critical rod position would be higher.
- b. At 10 7 amps, there are little or no effects from nuclear heat; therefore, the critical rod position should be the same as at 10 s amps,
- c. At 10 7 amps there are substantial effects from nuclear heat; therefore, the critical rod positions will be higher than at
] 10 s amps.
- d. At 10 7 amps, nuclear heat, xenon and the decade higher in power level will result in a higher critical rod position.
5.4 The reactor trips from full power, equilibrium xenon conditions. (1.0)
- Six hours later the reactor is brought critical at 10.samps on the
)
intermediate range. If power level is maintained at 10 samps which of the following statements is CORRECT concerning control rod motion?
, a. Rods will have to be withdrawn since xenon will closely follow its normal build-in rate. ,
- b. Rods will have to be inserted due to xenon decay.
- c. Rods will have to be rapidly inserted since the critical reactor will cause a high rate of xenon burnout.
- d. Rods will approximately remain as is as the xenon establishes its equilibrium value for this power level.
5.5 Figure 6.2-3 shows a graph of pump laws i.e., the relationship (1.0) between pump speed and other pump parameters. Which one of the following parameters is represented by curve 2?
- a. Power ,
- b. Flow Rate
- c. Voltage
- d. Discharge Pressure
- -- y. .- - m-. _.,_% _.w__...-_._ m._--.----,m.. . - . , _ , _ _ _ - . _ . . , , _ . _ . _ . - , , . _ , , _ . . - _ _ . , - .-,__-_.--.,..__.__m-m_._
3 5.6 Startup of a centrifugal pump with the discharge valve shut (1.0) is best characterized by which one of the following?
- )
- a. high motor current and high discharge pressure
- b. low motor current and low discharge pressure
- c. Iow motor current and high discharge pressure
- d. high motor current and low discharge pressure 5.7 Figure 43, " Surface Utilization vs Flow," represents the heat (1.0) transfer process in your OTSGs. Which of the following state-ments is CORRECT concerning Departure from Nucleate Boiling (DNB) Ratio as it relates to this Figure?
- a. DNBR of 1.0 occurs prior to nucleate boiling and cannot be shown on this figure,
- b. DNBR of 1.0 occurs between the nucleate boiling and the film boiling areas.
- c. DNBR of 1.0 occurs between the film boiling and the superheat areas.
5.8 Concerning the behavior of samarium-149, in the reactor, which (1.0) of the following statements is CORRECT?
- a. Most of the Sm produced comes directly from fission.
- b. Most of the removal of Sm is by radioactive decay.
- c. Sm reactivity is independent of flux once it has reached equilibrium,
- d. Equilibrium Sm is reached about 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> after the initial startup of the reactor.
,- i 4
5.9 An estimated critical boron concentration of 500 ppm was calculated using the information on Worksheet II (attached).
Assume the reactor achieved criticality at 80% withdrawn on Group 7. How would this critical rod position change (Group 7 more inserted, more withdrawn or no change) if each of the following conditions was different from that on Worksheet II?
Assume no boron change and consider each condition separately,
- a. Line 2.2.a. Last power level was 50% FP for 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. (.5)
- b. Line 2.2.b. Time shutdown was 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. (.5)
- c. Line 4.a. Average RC Temperature was 532F. (.5)
- d. Line 5. Group 8 (a 0% WD. (.5) 5.10 One of the characteristics of water is that it will hold gases (1.0) dissolved in solution. . Which of the following will INCREASE the concentration of dissolved gases in a quantity of water?
- a. Increasing the pressure and/or lowering the temperature.
- b. Decreasing the pressure and/or lowering the temperature.
- c. Increasing the pressure and/or raising the temperature.
- d. Decreasing the pressure and/or raising the temperature.
5.11 In the feedwater subsystem of the ICS, feedwater demand is (1.0) modified as a function of feedwater temperature. Select the CORRECT statement concerning this feedwater temperature compensation,
- a. Since feedwater temperature remains constant as power increases, additional heat must be provided in the OTSG for the steam to reach the proper superheat criteria.
- b. FW must be temperature compensated to account for the differing mass content of a gallon of water as temperature varies,
- c. The effect of croler FW entering the OTSG is that aspirating steam flow is reduced, header pressure decreases, and therefore, MW gen will decrease.
ci . The FW temperature compensation will affect the BTU limit calculation but have no affect on the FW demand signal.
. i 5
5.12 To maintain steam header pressure constant, it is necessary for (1.0)
OTSG steam pressure to by approximately 25 psig from no load to full load. This is in response to the laws of fluid dynamics which state that as the flow of steam increases in a steam line, the pressure drop experienced per unit line length .
- a. increase; increases
- b. increase; decreases
- c. decrease; increases
- d. decrease; decreases 5.13 Which one of the following is NOT part of the bases for the Tech (1,0)
Spec minimum temperature for criticality?
- a. Pressurizer is capable of being in an operable status with a steam bubble.
- b. Reactor pressure vessel is above its minimum RT NDT temperature,
- c. Protective instrumentation is within its normal operating range.
- d. Minimum DNBR is maintained during normal operation and short term transients.
5.14 You are plotting an inverse multiplication plot (1/m) during (1.0) fuel loading. When fuel is loaded so that the distance between the detector and the fuel steadily decreases, the 1/m plot will look like in Figure 5.21.
a.
b.
c.
d.
- __ =.
6 5.15 A synchroscope moving slowly in the SLOW direction (counter- (1.0) clockwise) indicates which of the following?
- a. Machine frequency higher than bus frequency, phases not matched.
- b. Machine frequency lower than bus frequency, phases not matched.
- c. Machine voltage higher than bus voltage, currents not in phase,
- d. Machine voltage lower than bus voltage, currents not in phase.
5.16 The Main Steam Line Break Accident forat the basis for the Shutdown (1.0)
Margin requirement at End-of-Life (EOL) conditions because:
- a. Beta-effective is at its maximum value,
- b. MTC is at its most negative value.
- c. Control rod insertion limits are most restrictive,
- d. Hot channel factors are at the most conservative values.
5.17 The process of hydrogen generation in the reactor building after (1.0) a LOCA which is controlled by the addition of caustic (NaOH) is:
- a. Radiolysis ,
- b. Zirc-water reaction
- c. Hydrogen coming out of solution
- d. Zine-boric acid reaction 5.18 Which of the following is NOT one of the conditions necessary (1.0) for brittle fracture? *
- a. plastic deformation at or below the yield point.
- b. temperature at or below the NOTT
- c. nominal stress level
- d. flaw such as a crack present i
a0 s~~m
, i 7
5.19 The startup, intermediate and power range channels all use boron (1.0) in their respective detectors (BF3 or boron lined). Which of the following is the CORRECT reason for use of boron?
- a. It reduces the critical volume (size) of the detector.
Detectorswhichrelysoleyongasigzationbyneutronsare much larger.
- b. Neutrons do not carry a net electric charge. Neutron detection must depend upon their interaction with target nuclei.
- c. Ionization of the Boron by neutrons is much more responsive and accurate than other ionizations such as neutron rhodium used in the in-core detectors.
- d. The neutron-boron reaction produces beta particles which have a much higher specific ionization than neutrons alone.
5.20 Power peaking is not a directly observable quantity, therefore, (1.5) limits have been established on the basis of Axial Power Imbalance produced by the power peaking. In addition to maintaining Axial Power Imbalance within prescribed limits, What three limitations on control rod movement ensure that hot channel factors are maintained?
5.21 Answer the following TRUE or FALSE concerning the Small Break LOCA analyses and reactor coolant pump trip criteria:
- a. The worst case SBLOCA was found to be a cold leg break in (0.5)
RCP discharge piping.
- b. The analyses assume that the RC pumps remain operative for some (0.5) time after the break and then are lost by some means (loss-of-off-site power, equipment failure, etc.)
- c. If the RC pumps remain operating throughout the blowdown and (0,5) reflood phase, the peak clad temperature critieria (PCT) would not be exceeded,
- d. With the RCPs lost and only one HPI pump operating, the PCT (0.5) criteria would be exceeded; with both HPI pumps operating, l it would not be exceeded.
i' 5.22 The RC pump power monitors have both high (262%) and low (20.9%) (0.5) setpoints. The low setpoint is based on the maximum time within which a trip must occur to provide DNBR protection for the four pump coastdown. Whrt is the high setpoint based on?
8 5.23 Select the CORRECT statement concerning pump cavitation. (1.0)
- a. Vapor bubbles are formed when the enthalpy difference between the pump discharge and pump suction exceeds the latent heat of vaporization.
- b. When the vapor bubbles enter a higher pressure region, the bubbles collapse which produces high pressure pulses or shock waves,
- c. Vapor cavities (bubbles) are produced when the localized pressure exceeds the vapor pressure at the existing temperature.
- d. As the vapor bubbles are discharged from the pump they impinge on downstream piping and valves causing water hammer.
END OF SECTION 5
9 6.0 PLANT SYSTEMS: OESIGN, CONTROL, AND INSTRUMENTATION (25.0) 6.1 Which of the following statements concerning the reactor (1.0) building isolation and cooling system (RBI & CS) interlocks is CORRECT?
- a. RBI and CS can be bypassed before it is actuated but only '
if RB pressure >2 psig.
- b. Only two of the three channels of actuation are required to be bypassed by the system logic for the operator to regain control of all components actuated by the RBI & CS.
- c. Once a component has been actuated to its ES position, it will remain in that position except the RB fans which can be shifted to FAST speed if required.
- d. The RBI and CS actuation will override any other signal except the control signal.
6.2 Select the INCORRECT statement concerning the Chilled Water (1.0)
System.
- a. The system supplies low temperature water to the Control
, Complex Air Handlers, Post Accident Sampling Coolers, Penetration Air Handlers, and Switchgear Room.
i
' c. The Water Chiller units can be cooled by either Nuclear Services Closed Cycle Cooling or Secondary Services Closed Cycle Cooling,
- d. Under accident conditions, only the Control Complex Air i Handler cooling function is required to be operable.
l 6.3 Select the CORRECT statement concerning the Heater Drain (1.0) and Vent System.
( a. The only heater drain valves that have control switches on the Main Control Board are the high level dumps for the MSR HP flash tanks and the high level dumps for the MSR LP Flash Tanks.
i b. A high level in the 1A, 18, 2A, and/or 2B heaters will j trip the main turbine.
- c. All condensate and feedwater heaters have extraction steam non return valves to prevent damage to the LP turbines,
- d. When the main turbine trips, the high level dump valves r on all condensate and feedwater heaters open and dump to '
l the main condenser.
l l
10 6.4 The synchronizing pin and bearing in the upper portion of the rotor (1.0) tube in the Control Rod Drive Mechanism (CRDM) is used to ensure...
- a. uniform rod speed over full travel
- b. proper direction of rotation
- c. both segment arms move together
- d. correct place relationship between individual rods within a group.
6.5 Which one of the following components of the EHC control oil (1.0) system are provided to maintain system pressure at approxi-mately 1250 psi?
- a. Unloader valves
- b. Relief valves
- c. High pressure accumulators
- d. Pressure switches 6.6 The Nuclear Services Closed Cycle Cooling System supplies (1.0) four separate coolers on each Reactor Coolant Pump and Motor.
LIST these four coolers.
6.7 Which one of the following makeup pump lube and gear oil system pumps (1.0) has N0 auto start provision?
- a. Main lube oil pump
- b. Main gear oil pump
- c. Backup gear oil pump
- d. Backup lube oil pump
11 6.8 Which one of the following statements is CORRECT regarding the (1.0) design of the emergency diesel generator air start system?
- a. There are two valves, one manual and the other remotely operated, in the interconnecting line between the two diesel air start systems,
- b. The manual air shutoff valve between the air reservoirs and its starting air manifold is provided with an alarm switch which actuates whenever the valve is not fully open.
- c. An air pressure low alarm (APLA) pressure switch alarms at 150 psig decreasing and auto starts the DC compressor motor.
- d. The pressure switch that auto starts and stops the AC motor (at 225 psig and 250 psig respectively) does not function when the DC motor is used; the DC motor must be started and stopped manually.
6.9 Four Post Accident Sampling System (PASS) containment isolation (1.0) valves are circled on the attached Figure 3. Of these, all but one must be deenergized during normal operation. Which o'ne?
- a. CAV-429
- b. CAV-430
- c. CAV-431
- d. CAV-432 6.10 Select the CORRECT statement concerning the Diesel Generator fuel (1.0) oil system.
- a. Sufficient fuel oil is stored in each unit's day tank for approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at name plate rating.
- b. The two 30,000 gallon fuel oil storage tanks have a double valve connection between them to provide additional fuel capacity to either diesel generator unit.
- c. Both fuel oil transfer pumps on each DG are DC powered to provide' redundancy in case of a station blackout.
- d. Care must be taken when filling the day tank from a storage tank since the day tank overflows to the waste system.
. i 12 6.11 Which of the following trip conditions is common to both a main (1.0) feedwater pump and a feedwater booster pump? (Remember: trip condition, not signal).
- a. Overspeed
- b. Low deaerator level
- c. Suction valves not full open
- d. Main steam line rupture matrix actuation 6.12 In the long term, following a SBLOCA, the BWST has reached its (1.0) 10-10 level alarm setpoint, but RCS pressure has remained above the shutoff head of the LPI pumps. LIST the sequence.of valve manipulations (by name or number) that are necessary to set up the LPI and HPI systems for continued injection into the RCS. (Six valves required.)
6.13 If both of the lights on a Bailey meter hand / auto control (1.0) station are lit:
- a. The station will control in either auto or manual, whichever was last selected.
- b. The station will not control in either auto or manual.
- c. The station will control in auto since auto overrides when both are selected.
- d. The station will control in manual since manual overrides when both are selected.
6.14 Which of the following statements is CORRECT concerning the (1.0) source range channels?
- a. The source range signals originate in two high sensitivity BF3 detectors that operate in the proportional range.
- b. The detectors are surrounded by lead shielding, thus making gamma compensation unnecessary.
- c. Due to the low level pulses from the detectors, ,
preamplifiers located in the RPS cabinets are required to provide impedance matching.
- d. Due to their sensitivity, long term outages will have no noticeable effect on the range of indication.
. i 13 6.15 Assume the reactor tripped on high Th of 618'F. After Th (1.0) stabilized at a lower value (550 F) what would you expect to see on the Output State Lamp and Output Memory Lamp for the Th bistables in each RPS cabinet?
- a. both lamps dim I
- b. both lamps bright
- c. Output State Lamp - dim Ouput Memory Lamp - bright
- d. Output State Lamp - bright Output Memory Lamp - dim 6.16 Which one of the following is CORRECT concerning the fuel handling (1.0) controls?
- a. Simultaneous movement of the bridge, trolley and hoist is permitted only with the fuel grapple mechanism disengaged.
- b. Movement of the bridge or trolley is not possible unless the grapple (engaged or disengaged) is raised entirely up into the mast.
- c. The grapple mechanism cannot be disengaged by operator error or electric or hydraulic failure when the grapple is loaded.
- d. A limit switch is provided to prevent raising the fuel assembly above minimum shielding depth.
6.17 Select the CORRECT statement concerning the FW Pump Discharge (1.0)
Crossover Valve, FWV-28.
- a. During normal full power operation, the valve is open with its control switch in AUTO position,
- b. On reset of the steam line rupture matrix it will auto-matically open.
- c. It will auto close on actuation of either steam line rupture matrix or ES channels A and B.
- d. The auto open signal comes from a pressure switch on the main feedwater pump control oil pressure.
6.18 a. LIST by name or number the valves that will be isolated (2.0) following actuation of the Steam Line Rupture Matrix.
Consider either OTSG.
- b. What are the two conditions, either of which must be (1.0) satisfied in order to reopen any of the isolated valves?
14 e
6.19 During a " rapid bus transfer", which one of the following source (1.0) feeder circuit breaker operations will occur (within 6 cycles)?
- a. both the outgoing and the incoming will close
- b. both the outgoing and the incoming will trip
- c. the outgoing will trip and the incoming will close simultaneously
- d. the outgoing will trip before the incoming will close
- e. the outgoing will trip after the incoming closes 6.20 Which one of the following choices of depressing STOP push- ^}
buttons will, by itself, trip the ciesel generator output breaker?
- a. stop pushbutton in the control room e/ b. one stop push button on the diesel gaugeboard
%J q c. both stop push buttons on the diesel gaugeboard
- W d. stop pushbutton on the diesel generator local control panel by the D-G air start compressor 6.21 Which of the following statements about RB Purge control is CORRECT? (1.0)
- a. Both purge supply fans must be operating to permit start of the exhaust fans.
- b. Exhaust duct temperature greater than 135*F will shut down the exhaust fans.
- c. RB purge exhaust fans are operated from the "ES" panel and the isolation valves are operated from the H&V panel.
- d. Purge valves are automatically closed and supply and exhaust fans trip on a HIGH radiation alarm from RM-A-1.
15 6.22 Which one of the following is an interlock provided on the waste (1.0) gas disposal system at Crystal River?
- a. If a waste gas decay tank discharge exceeds 50 cfm a flow sensor will close that tanks discharge valve (WDV-436, WDV-437, or WDV-438).
- b. High Radiation on RM-A-11 will close the waste gas decay tank outlet to the recycle valves (WDV-393, WDV-394, and WDV-395).
- c. Each waste gas decay tank inlet valve is interlocked so it cannot be opened unless the outlet valves are open for that tank.
- d. High Radiation on RM-A-2 will close the waste gas discharge auto control valve (WDV-439).
- e. A pressure greater than 80 psig in all waste gas decay tanks will close ventilation dampers D-29 (supply) and D-36 (exhaust) isolating the waste gas surge tank and decay tank area.
6.23 Select the CORRECT statement concerning instruments and controls (1.0) associated with the Fuel Handling Bridge,
- a. The selsen unit consists of a synchro transmitter which is used to indicate the relative position of the Trolley.
+
- b. The Z-Z tape is a stainless steel measuring tape that provides the interlock that actuates the " Grapple Tube Up" Light.
- c. The weight range over which the Dillon load cell is indicating is manually selected from the inside of the control panel,
- d. The main bridge is located in the East-West direction by means of a sight window which the operator lines up against the fixed scale on the rails.
END OF SECTION 6
16 7.0 PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL (25.0) 7.1 The Immediate Actions, in response to High Alarms from Atmospheric (2.5)
Radiation Monitors RM-Al through RM-AS, require you to " ensure stopped" various ventilation fans. Match the fans you are required to ensure stopped with the appropriate monitor and procedure.
NOTE: Some fans may be required in more than one procedure,
- a. RM-Al (AP-241) 1. AHF-9A & 98
- b. RM-A2 (AP-242) 2. AHF-10
- c. RM-A3 (AP-243) 3. AHF-11A and 11B
- d. RM-A4 (AP-244) 4. AHF-17A and 17B -
- e. RM-A5 (AP-243) 5. AHF-19A and 198
- 6. AHF-20A and 208 (or in slow speed)
- 7. AHF-30
- 8. AHF-34
- 9. AHF-44A and 448 7.2 List your immediate actions in response to an alarm from RM-L7. (0.5)
- 7. 3 Which of the following is an immediate action required (1.0) in AP-320, " Loose Parts monitoring system".
- b. Notify I&C technician to re.aove the LPMS tape deck.
- c. Adjust "FS range" switch on affected channel signal amplifier until alarm clears.
- d. Select the alarming channels to " audio matrix" position.
17 7.4 The following is the first immediate action under AP-380, (1.0)
" Engineered Safeguards system actuation". IF SRMA present OR RC PRESS < 1500 psig, THEN depress "HPI Actuation" Pushbutton "A" and "B". What are the Remedial Actions associated with this step?
- 7. 5 LIST your Immediate Actions to AP-450, " Emergency Feedwater (2.0)
Actuation."
- 7. 6 The nuclear services cooling water to the CRD stators should (1,0) be secured under which of the following conditions.
- a. Less than three stators are energized and the reactor is NOT critical.
- b. RC system temperature is between 200'F and 300 F.
- c. Air temperature around the drives in the service structure is less than 150 F.
- d. Any time all CRDs are deenergized for an extended period of time.
7.7 If OTSG's are available, Step 14.a of AP-380 (see Figure 5 & 6 (1.0) attached) requires the starting of a number of RCPs in a particular loop configuration. (NOTE: Some information has been deleted from Figure 5 & 6). If the RC pressure is 300 psi and RC temperature (Tc) is 300*F, you should:
- a. start one pump in either loop
- b. start one pump in each loop
- c. start two pumps in either loop
- d. start two pumps in each loop
- e. Refer to AP-530 7.8 Annunciator Window I-2-3 on the ICS Panel is labeled " Pressure (1.0)
Transient in Progress." Which one of the following is a CORRECT indicated condition for this annunciator?
- a. Pressurizer Safety Valve Open
- b. High RC pressure at low temperature (NOTT)
- c. High RCS pressure (above trip setpoint)
18 l 7.9 ICS procedure, OP-501 states in part, "If operating signal source (1.0) malfunctions make signal source transfer necessary, transfer to another signal source should be done ... " Which one of the following CORRECTLY completes this statement?
- a. immediately after placing the affected ICS station in HAND.
- b. immediately, regardless of ICS operating mode.
- c. only after checking the computer for a valid alternate signal and placing the affected ICS station in HAND.
t
- d. only after checking the computer for a valid alternate signal; affected ICS station may be in HAND or AUTO.
7.10' hich one of the following is an appropriate "immediate" action (1.0) according to EP-120, " Inadequate Shutdown Value?"
- a. Stop cleanup.
- b. Establish letdown flow to MUT > 40 gpm.
- c. Start boric acid pump CAP-3A or 3B.
- d. Verify reactor trip, go to VP-580.
7.11 Which one of the following is CORRECT concerning the operation of (1.0) the ICS main feedwater pump speed control station?
- a. Tripping of the associated feedwater pump will inhibit
" auto" operation and light both " auto" and " hand" lamps.
- b. Care should be taken when simultaneously transferring both Loops "A" and "B" main feedwater pump control stations to " auto".
- c. " Meas-VAR" position indicates feedwater demand error when the main block valves are shut.
'l o '
19 7.12 Which one of the following is a CORRECTLY stated Limit and (1.0)
Precaution as contained in OP-605, "Feedwater System",
- a. If at any time emergency FW pump discharge drops to zero pressure, immediately secure the pump under all operating conditions.
- b. If at any time emergency FW pump discharge drops to to zero pressure, immediately secure the pump, except under emergency operation.
- c. The motor-driven emergency FW pump (EFP-1) will not auto-start if emergency diesel generator 38 (EDG-38) is running and closed onto its respective bus,
- d. The motor-driven emergency FW pump (EFP-1) will not auto-start if emergency diesel generator 3B (EDG-38) is running with its output breaker open.
7.13 Which one of the following is CORRECT concerning the bridge and (1.0) trolley limit switches and interlocks?
- a. All limit switches may be bypassed with the exception of the proximity switches,
- b. A proximity switch on the right side of eacn bridge prevents the two bridges from running into each other.
- c. The auxiliary bridge has a right limit switch to prevent running into the reactor vessel head locating studs.
- d. To move the trolley the fuel grapple must be up and disengaged.
7.14 Who determines whether a person is a " qualified bridge operator?" (1.0)
- a. CN0
- b. Shift Supervisor on duty
- c. Training Manager
- d. Operations Superintendent
. ~
, _ _ _ , _ _ . . . . , _ . _ m _- _ _ _ . , ._ ____ _ . - - , , . - _ _ _ _
20 7.15 Under which of the following conditions are you required to (1.0) manually trip the reactor during a startup?
- a. A main steam isolation valve goes closed.
- b. The reactor goes critical with Group 5 below insertion limits.
- c. A startup rate > 1 DPM is achieved.
- d. Pressurizer level goes above 290 inches.
7.16 With the reactor < 40% FP, which of the following operations (1.0) would NOT require bypassing the RCP Power Monitors?
- a. Paralleling an EDG to a 4160V bus,
- b. Switchover between startup and unit auxiliary transformers.
- c. Energizing an idle RCP.
- d. De-energizing an operating RCP.
7.17 If loss of seal injection occurs on a secured RCP (with plant (1.0) operating or in hot standby) which of the following actions is required?
- a. No action required if seal return temperature remains
< 180 F.
- b. Close the controlled bleed off valve if seal return temperature reaches 155"F.
- c. Immediately shut seal injection valve, start standby makeup pump, then reopen injection valve,
- d. Secure remaining pumps until cause of loss is determined.
7.18 An Immediate Action to AP-770, " Emergency Diesel Generator (1.0)
Actuation" is: -
IF under voltage exists on 4160V ES bus, then ensure affected bus Is energized by EDG.
What are the Remedial Actions associated with this step?
l l
l 21 7.19 Which one of the following " Radiation Area" definitions (1.0) means the same as that given in RP-101, " Radiation Protection Manual"?
- a. any area where the dose rate exceeds five mrem /hr or where, in any five (5) consecutive day period, exceeds 100 mrem /hr at any time.
- b. any accessible area where a major portion of the body could exceed a dose of five mrem in any one (1) hour, or in any five (5) consecutive days a dose in excess of 100 mrem.
- c. any accessible area where any portion of the body could exceed a dose rate of five mrem /hr or where, in any five (5) consecutive day period, could exceed a dose rate of 100 mrem /hr at any time.
- d. any area where the dose rate to any portion of the body could exceed a dose of five mrem in any one (1) hour, or in any five (5) consecutive days a dose in excess of 100 mrem.
7.20 Which one of the following provisions is the responsibility (1.0) of a reactor operator leaving the 95' elevation control complex RCA as part of the first step in his whole body frisk?
- a. Ensure the equipment is turned on and operating on the highest scale.
- b. Ensure proper operation of the instrument by noting that the instrument has been source checked.
- c. The background reading should be less than 300 dpm/100 cm2,
- d. Ensure the beta window control is in the open position.
22 7.21 Which one of the following is CORRECTLY stated regarding a permis- (1.0) sible dose to an operator in a restricted area as specified in 10CFR 20.
- a. Under non-accident conditions, the operator is permitted to receive no more than 7 rems per calendar quarter to each hand and to each foot.
- b. Under non-accident conditions, the operator is permitted to receive no more than 1% rad of beta per calendar quarter to the lens of the eye.
- c. Under accident or emergency conditions, the operator is permitted to receive up to 25 rem once in a lifetime exposure.
- d. Under accident or emergency conditions, the operator is permitted to receive up to 100 rem once in a lifetime exposure.
7.22 According to EP-290, " Inadequate Core Cooling", the hot leg vents (1.0) should be used under two separate conditions. Which of the following choices states those conditions. (See page 7 of EP-290 attached for reference to " Regions").
- a. Pzr press >1500 psig; press and temperature in Region 2
- b. Pzr press >1500 psig; subcooling margin <50 F
- c. Pzr press >1500 psig; press and temperature in Region 3
- d. Pzr press >2300 psig; subcooling margin <50*F
- e. Pzr press >2300 psig; press and temperature in Region 3 7.23 Select the CORRECT statement concerning the " Waste Gas Disposal (1.0)
System," OP-412.
s
- a. The " Warning" and "High" setpoints on the radiation monitors are adjusted by Chem Rad and verified by the Shift Supervisor.
- b. If the meteorological instrumentation is inoperable, wind speed, direction and delta temperature may be estimated and the release may proceed.
- c. Any waste gas tank to be released to the environment must be recirculated through at least two tank volumes prior to sampling.
- d. It is not required to completely isolate the tank, nor i
initiate a Release Permit when discharging a waste gas decay tank to containment.
END OF SECTION 7 1
l 1
23 8.0 ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS (25.0) 8.1 During a plant startup with the reactor at 2% power, one power (1.0) range channel (NI-6) for example), is found to be inoperable.
Which of the following statements is CORRECT? Refe- to the attached Tech Specs.
- a. Operation above 5% Rated Thermal Power is not allowed until the inoperable channel is repaired and declared operable,
- b. If NI-6 is placed in a tripped condition AND the other three channels are operable, you must reduce the Nuclear Overpower Trip Setpoint to 1 85% and Thermal Power is restricted to
< 75%.
- c. If NI-6 is placed in a tripped condition AND the other three channels _are operable, operation to 100% Rated Thermal Power is unrestricted.
- d. The only restrictions on proceeding to 100% Rated Thermal Power are that NI-6 be placed in a tripped condition and Quadrant Power Tilt be monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
8.2 Which of the following statements is CORRECT concerning the (1.0)
Quandrant Power Tilt (QPT)?
- a. If QPT exceeds the maximum limit of 20.0, the reactor must be immediately shutdown.
- b. If misalignment of a control rod causes the QPT to exceed the transient limit, thermal power must be reduced within 30 minutes.
- c. No ACTION is required within one hour regardless of the QPT limit exceeded (steady state, transient, or maximum).
- d. If QPT exceeds the steady state limit, but is less than the transient limit, operation may continue indefinitely only up to 60% allowable for the RCP combination.
l
D
- 24 1
8.3 Which one of the following is CORRECT regarding EM-201, " Duties (1.0) of an Individual Who Discovers an Emergency"?
- a. Any individual discovering an emergency condition has the authority to implement this procedure to the fullest extent of his qualifications.
- b. Primary examples of emergency conditions covered by this procedure are tornado, acid and caustic spills, security threats and any other emergencies not involving radioactive material.
- c. An individual who discovers an emergency condition shall notify the control room and the nuclear plant manager or his designee.
- d. The individual should take any immediate action that will minimize the emergency except extinguishing fires; fires shall only be fought by the fire brigade members.
8.4 According to administrative procedure AI-100, an individual (1.0) should not be permitted'to work more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any
-hour period (excluding shift turnover time) unless authorized at the . level or above. (Choose the correct pair below.)
- a. 48, Nuclear Operations Superintendent
- b. 48, Nuclear Plant Manager
- c. 72, Nuclear Operations Superintendent _
- d. 72, Nuclear Plant Manager 8.5 Which one of the following type of procedures must be step- (1.0) by-step (as opposed to guidance) according to AI-500, " Conduct of Operations?"
- a. Those which directly effect the mitigation of unusual events.
- b. Those which directly effect containment integrity.
- c. Those which provide for coping with plant emergency conditions.
- d. Those which provide the details of on-shift practices.
25 8.6 An event in process which indicates a potential degradation of (1.0) the level of safety of the plant is classified as:
- a. an unusual event
- b. an alert
- c. a site emergency
- d. a general emergency 8.7 If you are escorting a visitor while you are off shift when a Site (1.0)
Emergency is declared, you must:
- a. Direct the visitor to the PEA by the most direct route.
- b. Escort the visitor off site.
- c. Direct the visitor tofremain with you on site.
- d. Escort the visitor to the control room.
8.8 Immediate notification of NRC and DHRS is required if the release (1.0) of radioactive materials in concentrations which, if averaged over a perid of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, would exceed times the limits specified for such materials in Appendix "B", Table II of 10CFR 20; damage to property in excess of $ . Fill in the blanks with the CORRECT information by choosing ONE of the below combinations.
- a. 500; or; 2,000
- b. 500; and; 2,000
- c. 5,000; or; 200,000
- d. 5,000; and; 200,000 8.9 TRUE OR FALSE
- a. In order to raise a new fuel assembly or dummy fuel assembly. (0.5) with the new fuel elevator, it requires the approval of either the Refueling Supervisor OR the Reactor Specialist.
- b. In order to raise an irradiated fuel assembly with the new (0.5) fuel elevator, it requires the approval of both the Refueling Supervisor AND the Reactor Specialist.
r-26 8.10 Complete the following statement by selecting the CORRECT fill (1.0) in from below.
"When two (2) irradiated fuel assemblies are being handled within the FTC, a r.linimum separation of ft. shall be maintained between the assemblies at all times,
- a. 3
- b. 5
- c. 10
- d. 23 8.11 Answer the following TRUE or FALSE regarding various Tech Spec Surveillance Requirements.
- a. While subcritical in Mode 2, verifying that the regulating (0.5) rod groups are above the insertion limits is an acceptable method of determining that the shutdown margin Tech Spec is met.
- b. Since APSR's do not insert on a reactor trip, they have no (0.5) surveillance requirements regarding operability (except for their position indication system).
- c. Even though the core flood tank isolation valves are open with (0.5) their breakers in " Lock Reset" (Modes 1 & 2), a surveillance requirement exists for verifying each isolation valve is open.
- d. Surveillance requirements have to be performed on inoperable (0.5) equipment if the equipment is inoperable due to an auxiliary system failure that does not prevent operation of the equipment (for example, air compressor failure on a DG renders the diesel INOP).
8.12 What is the time interval at which a short-term instruction (1.0) automatically expires?
- a. whenever reissued
- b. 30 days after issue ;
l
- c. 90 days after issue l l
- d. at the beginning of the next refueling outage
4 d
{ 27' i
8.13 Crystal River operating policy gives guidance on the primary to (1,0) 4 secondary steam generator tube leakage at which consideration should be given to shutting down the plant? What is that leak rate?
- a. anything greater than zero, since it is pressure boundary 1 leakage
- b. .3 gpm
- c. 1 gpm
- d. 10 gpm 8.14 The attached Figure 2 is the Crystal River Technical Specifications (1.0)
, bases Figure 2.1. Which one of the following statements is CORRECT concerning these curves?
- a. These curves represent the~ conditions at which a minimum DNBR i of 1.30 is predicted at the maximum possible thermal power for
, the number of reactor coolant pumps in operation.
l
} b. For each of these curves, a pressure-temperature point below j and to the right of the curve would result in a DNBR greater ;
than 1.30. '
I
- c. These curves include the potential effects of the ejected i
control rod and reactor coolant pump locked rotor accidents.
l d. The DNBR curve for four pump operation is more restrictive
. than any other reactor coolant pump situation.
8.15 Only one of the following components.has a maximum boron (1.0)
{ concentration specified in Technical Specification for the i operational MODE indicated. Which one?
I a. Pressurizer - MODE 2 l b. Concentrated boric acid storage system - MODE 3
! c. Core flood tank - MODE 4
- 4
- d. 8WST - MODE 5 T-
- r i
i
}
't 1
i F
l 28 j 8.16 DG A, which supplies ES 4 KV Bus A is INOPERABLE. LPI pump B (1.0) supplied by ES 4 KV Bus B is INOPERABLE. The Tech Specs for ECCS subsystems and AC Sources are attached. Which statement is CORRECT concerning continued Operation in Mode 1?
- a. The Action Statements for both the LPI pump and the DG are applied independently, each must be restored to OPERABLE in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
- b. Since the DG is required in Mode 4 and the LPI pump is not, the Unit must be taken to Mode 4 within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
- c. TS. 3.0.3 applies; it requires action to place the unit in a mode in which the specification does not apply within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
- d. T.S. 3.0.5 applies; it requires action to place the unit in a mode in which the specification does not apply within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
8.17 If the shutdown margin is less than 1% ak/k in Mode 5, the (1.0) required action is and continued boration at
> gpm of 11,600 ppm boric acid solution or its equivalent until the required SHUTOOWN MARGIN is restored.
- a. immediately initiate, 1
- b. within 15 minutes initiate, 10
- c. immediately initiate, 10
- d. within 15 minutes initiate, 1 8.18 During hydrostatic testing operations above system design pressure, (1.0) what is the maximum temperature change permitted by Tech Specs in any one hour period?
- a. 5*F
- b. 50 F
- c. 100'F
- d. no limit
O 29 8.19 The Tech Spec ECCS limits on BWST minimum volume and boron (1.0) concentration ensure that: (Select one of the following).
- a. sufficient borated water is available within containment to absorb 99% of the iodine released in a LOCA.
- b. the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> thyroid dose at the site boundary will be consistent with the analysis presented in the FSAR for postulated steam generator tube rupture.
- c. the reactor coolant system can be cooled down to less than 280 F from normal operating conditions in the event of a total loss of off-site power concurrent with a LOCA.
- d. the reactor will remain subcritical in the cold condition following mixing of the BWST and the RCS water volumes with all control rods inserted except for the most reactive control assembly.
8.20 a. What is the only condition under which the designated (1.0)
" Operator at the Controls" can leave the red-carpeted general area for non-emergency purposes?
- b. In the event of an emergency affecting the safety of (1.0) operations, the " Operator at the Controls" may momentarily be absent from the general area in front of the control board provided .... (Complete this sentence).
8.21 When a reactor trip or plant shutdown occurs, the Nuclear Shift Supervisor first ensures that the plant is placed in a safe condition by having the necessary operations performed in accordance with approved procedures.
- a. He then makes 5 notifications: List them. (1.0)
- b. Explain the NSS's responsibilities concerning Form 912212, (1.0)
Reactor Trip and Shutdown Report.
8.22 When performing a valve lineup or power supply breaker position (1.0) verification, what are the two conditions that should not be signed off?
END OF SECTION 8
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3.3 1.4 1.5 1.5 1.7 1.s Entropy l
T ABLT D 1. '
P8operties of Dr5 Satur.im! Steam
- Prenure o,
7 amp.
Erek volums k atha'r)
Eat tor.'
Penn .
" *I hi Sai Se-e liewd verce leewd I P Sei vapoe Set I.g d Ever ht ~
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', ', 4, 4, 8, 8, 8, 1.0 101.74 0.01614 333 6 69 7D 10 %.3 l106 0 0 1326 f.84%
20 126.0k 0 0162.1 173 7.1 93 99 1022.2 l.9782 30 1414k 1116.2 0.1749 1.7451 1.9200 0 01610 116 71 10937 1083.2 1122 6 02006 1.6455 40 152 97 0.01636 90 63 120 h6 100e 4 1.8863 1127.3 0.2196 1.6421 5.0 162.24 0 01640 73.52 1.8625 13u 13 1001.0 1131.1 0 2347 2.6094 1.8448 6.0 170D6 0 01645 61.96 137.96 996.2 1134.2 0.2472 1.5420 7.0 1 % 85 0 01649 53 64 1.8292 144 % 992.5 11 % .9 0.2581 1.5586 8.0 182.86 0.01653 47.34 1.8167 150 79 985.5 1139.3 0.2674 1.5%)
9.0 186.26 0.01656 42 40 1.8057 156.22 965.2 1141.4 0.2759 1.520) 10 193.25 0.01659 38 42 1.7962 161.17 982.1 1843.3 0.2835 1.5041 1.78 4 14.696 212 00 0.01672 26.80 180 07 970.3 1150 4 0.3120 1.4446 15 213.03 0 0I672 26.29 1.7566 ist 11 969.1 1150 8 0.3135 1.4415 20 227.96 0.01683 20 089 1.7549 19e 16 9601 81 % .3 0.3356 1.3962 25 240.07 0 01692 16303 l.7319 206 42 952I 1160 6 0.3533 1.3606 1.7139 30 250 33 0.0170! 13.746 216.82 945.3 1864.1 0.3680 1.3313 1.6993 35 259.28 0.01706 11.89b 227.91 939.2 1867.1 0.3807 1.3063 40 267.25 0.01715 10 496 1.6870 236.03 933.7 l169.7 0.3919 1.2844 45 274.44 0.01721 9.401 1.643 243.36 928.6 1172.0 0.4019 1.2650 50 281.01 0.01727 1.6669 8.515 250.09 924.0 1874.1 0.4110 55 287.07 1.2474 1.6585 0.01732 7.787 2%.30 919.6 1175.9 0.4193 1.2316 1.65&i 60 29271 0.0173F 7.175 262.09 915.5 5177.6 0.4270 1.2168 1.6436 65 297.97 0.01743 6.655 267.50 911.6 1179.I 0.4342 1.2032 1.6374 10 302 92 0.01748 6.206 272.61 907.9 1I80.6 0.4409 1.1906 l.6315 75 307.80 0.01753 5.816 277.43 904.5 1881.9 0 4472 1.1781 1.6259 80 312.03 0.01757 5.472 282 02 901.1 1883.I 0 4531 1.16 % 1.6207 85 316.25 0.01761 5.168 286.39 897.8 Il84 2 0 458? 1.1571 1.6158 90 320.27 0.01 % 6 4.8% 290.56 894 7 1185.3 0 4641 1.1471 1.6812 95 324.12 0.01770 4.652 294.56 891.7 l 186.2 0.4692 1.1376 I.6066 100 327.81 0.01774 4.432 298.40 888.8 1887.2 0 4740 1.1286 I.4026 150 334 77 0.01782 4.049 305.66 883.2 1188.9 0 4832 1.1117 1.5946
TABLE D.la Properties of Dr> Saturated Steam trontieurd, Pressure 3, sen r. i. e tnineir. tni,or-7emr.
"" i 8., s.i s.i s.-
,sei e..e s.
i.w.e ..co, i.oie ti.c ,,,,,, ,,,, ,,,,,
l r a e r *, ho an ha s i
su s, ,
i 120 341.25 0 01789 3.72k 312 44 877.9 1890 4 0 4916 1.09c2 1.587b 130 347.32 0 01796 3 455 318.81 872 9 1891.7 0 4995 1.0817 1.5812 140 353.02 0.01802 3.220 324 82 868.2 1893.0 0.50#.9 1.0682 1.5751 150 356 42 0 01809 3.015 330 51 863.6 1194 1 05136 1.0556 1.% 94 160 % 3.51 0 01815 2 8.14 335 93 859.2 1195 1 0.5204 1.0436 1.5640 170 36b 41 0 01822 2.675 341.09 BM9 1896 0 0.526f. 1.0324 1.5590 l80 373 06 001827 2'532 346 0.1 850 8 1196.9 0.5325 10217 1.5542 190 377.51 0.01833 2.404 350 79 846 8 1897.6 0 53bi 1.0116 1.5497 200 381.79 0 01819 2.28k 355.36 843 0 11 % 4 0.5435 1.0018 l.5453 250 400.95 0 01865 I.8438 376 00 825.1 1301.1 0.% 75 0 95816 1.5263 300 417.33 0 01890 't.5433 393.84 809 0 1202 8 0.5879 0 9225 1.5104 431.72 0 019I3 l.3260 409.69 794 2 1203.9 0.6056 0 8910 1.4966 350 400 444.59 0.0193 1.1613 424 0 780.5 1204.5 0.6214 0.8630 1.4844 450 4%.28 0.0195 1.0320 437.2 767.4 1204 6 0.63 % 0.8378 1.4734 467.01 0 0197 0 9278 449.4 155 0 1204 4 0.6487 0.8147 1.4634 500 550 476.94 0 0199 O b424 460 8 143.1 1203.9 0 6606 0 7934 1.4542 600 486.21 0 0201 0.1696 471.6 731.6 1203.2 0 6720 0.7734 1.4454 650 494.90 0.0203 0.7083 481.8 720.5 1202.3 0.6826 0.7546 1.4374 100 503.10 0.0205 0.6554 491.5 109 7 1201.2 0.6925 0.7371 1.4296 750 510.86 0.0207 0.6092 500 8 699.2 1200.0 0.7019 0.7204 1.4223 800 518.23 0.0209 0.5687 509.7 688.9 1198.6 0.7108 0.1045 1.4153 850 525.26 0.0210 0.5327 518.3 678.8 1l97.1 0.7194 0.6891 1.4085 900 531.98 0.0212 0.5006 526.6 #88 1195 4 0.7275 0.6744 1.4020 950 5% 43 0.0214 0.4717 $34 6 659.1 1193.7 0.7355 0 6602 1.3957 1000 544.61 0.0216 0.44 % 542 4 649.4 1191.8 0.7430 0.6467 1.3897 l100 5 % .31 0.0220 0.4001 557.4 630 4 1187.7 0.7575 0.6205 1.3780 1200 % 7.22 0.0223 0.3619 571.7 611.7 1183 4 0.7711 0.59 % 1. % 67 1300 577 46 0 0227 0.3293 585 4 593.2 1178e 0.7840 0.5719 1.3559 1400 587.10 0 0231 0.3012 $98.7 574.7 1873 4 0.7963 0.5491 1.3454 1500 5%.2.1 0.0235 0.2765 611.6 5%.3 1167.9 0.8062 0.5269 1.3351 2000 635.82 0.0257 0.1878 671.7 463 4 1135.1 0.8619 0.4230 1.2849 2500 M8.13 0.0287 0.1307 730.6 360.5 1091.1 0.9126 0.3197 1.2322 3000 695.36 0.0346 0.0858 802.5 217.8 1020.3 0.9731 0.1885 1.1615 3206.2 705.40 0 0503 0.0503 902.7 0 902.7 1.0580 0 1.0500 l
I
T ABLf. D.lb Properties of Dr3 Saturated Siesm(cumim. cts
- Temperature Embstr. . Emtors
$ record solume A b' 1smr. Sei So- Set
+7 P"" Sei Set Set l'er e,,,,, tsar ,, p,,
P t,q v.4 . . po, i.evie ,,,,,
ha h a sa n
', h o s o e e 's a 00s4H 0 01602 3306 0 00 1075ti 1075.8 0 0000 2 1871 2.1877 32 3.02 1014.1 1077.1 0.0061 2.1709 2 1770 35 0.09995 0 01602 2947 0 12170 0 01602 2444 8 05 1071.3 1079.3 0 0162 2.1435 2 1597 40 45 0I4752 0 01602 20 % 4 13.06 10664 1061.5 0.0262 2.1161 2.1429 50 O l?til 0 0160) 1703.2 16 0i 106$ 6 10631 00%1 2 0903 2.1264 28.0t- 1059.9 1088 0 0 0555 2.0393 2 0948 60 02%) 0 01604 1206.1 1.990: 2.0647 0 %)I 0.01606 867.9 38 04 1054 3 1092.3 0 0745 10 1.942b 2.0360 0.0160b 633.1 48 02 1046 6 1096 6 0 0932 80 0 5069 0.6962 0.01610 4680 57.99 1042 9 1100.9 0.1Il5 1.8972 2 0087 90 l.8531 1.9826 0 9492 0.01613 350 4 67.97 1037.2 1105.2 0 1295 100 0 01617 265 4 77.94 1031.6 1109.5 0.1417 l.8106 1.9577 110 1.27 4 1.9339 203 27 87.92 1025.6 1813 7 0.1645 1.% 94 120 1.6924 0.01620 157.M 97.90 1020.0 t il7.9 0.1816 1.7296 l.9112 130 2.2225 0.01625 107.89 1014l 1122.0 0 1984 1.6910 1.8894 140 2 8886 0 01629 123.01 1006.2 1126.1 0.2149 1.6537 1.8685 150 3.716 0.016M 97.07 117.89 77.29 127.89 1002.3 1830.2 0.2311 1.6174 f.8485 160 4 741 0 01639 170 5.992 0 01645 62.06 137.90 996.3 llH 2 0.2472 1.5822 1.8293 147.92 990.2 1138.1 0.2630 1.5480 1.8109 ISO 7.510 0.01651 50.23 964 1 1142.0 0.2785 1.5147 1.7932 190 9.339 0 01657 40.96 157.95 0.01663 33.64 167.99 977.9 1145.9 0.2938 1.4824 l.742 300 11.526 178.05 971.6 1149.7 0.3090 1.4508 1.7598 210 14.123 0.01670 27.82 180.07 970.3 1150 4 0.3120 1.4446 1.7566 212 146% 0.01672 26.30 23 15 188 13 965.2 1853 4 0.3239 l.4201 1.1440 220 17.186 0.01677 19.382 196 23 958.8 1157.0 0.3387 1.3901 I.7288 230 20.780 0.01684 0.01692 16.323 206.34 952.2 1160.5 0.3531 l.M09 1.7140 240 24.969 216.48 945.5 1864 0 0.3675 1.3323 1.6998 250 29.825 0.01700 13.821 II.%) 228.64 9 38.7 1167.3 0.3817 l.3043 l.6860 260 35.429 0.01709 238.84 931.8 1870.6 0.3958 1.2%9 1.6727 270 41.~858 0.01717 10.061 8.645 249.06 924.7 1873.8 0.4096 1.2501 I.6597 280 49.203 0.01726 7.461 259.31 917.5 llM.8 0.42M l.2238 1.6472 290 57.5 % 0.01735 300 67.013 0.01745 6 466 269.59 910 l 1179.7 0.4M9 l.1980 1.6350 310 77.68 0.01755 5.626 279.92 902.6 1182.5 0.4504 1.1727 l.6231 320 39.66 0.01%$ 4.914 290.28 894.9 1885.2 0.4637 1.1478 1.6115 330 103 06 0 01776 4.307 300.68 887.0 l187.7 0 4769 1.1233 1.6002 340 118 01 0.01787 3.786 311.13 879.0 1190 l 04900 1.0992 1.589I
TABLE D Iti Properties of Dry Saturated Steam tenninnued.
lemperature 3, scuit...oi me imm. irs a mor.
1emp.
.r P"",
P' se su su I"r sei sei tur so he..e ..co, i ..e uro, i.e .e ..po,
- r *, ', 8, A. 4, 8, s. 8, 350 134 6) 0 01799 3.34 321 63 870 7 1192.3 0.5029 1.0154 1.576.1 360 153 04 0 01611 2 95' 33218 852 1194 4 0 5156 10519 1 5677 -
370 173.31 0 01621 2 625 34: 79 853 $ 1896 3 0 526o I02b? l.5573 380 195.77 00164 2.335 353 45 SM 6 1196 1 0.5413 1.0059 1.5471 390 220.37 0 01850 2 0th 3e411 8354 1199 6 0.5539 0 9632 1.5371 400 247.31 0.01864 1863) 374 97 826 0 1201.0 0.5664 0 9606 1.527 410 276 75 001876 1.6700 385 8.1 816 ) 1200 1 0.5786 0 9366 1.5174 420 30683 0 01894 1.5000 3%17 806 3 1203 1 0.5912 0916e 1.5076 430 343.72 0 01910 1.3499 407.79 796 0 1203.6 0 6035 0.8947 1.4982 440 381.59 0.01926 1.2111 4I8 90 785 4 1204.3 0.61 % 08730 1.4887 450 422 6 0.0194 1.0993 430.1 774.5 1204 6 0.6280 0.8513 1.4793 460 466.9 0.0196 0.9944 441 4 763 2 1204 6 0 6402 0 8296 1.4700 470 514 7 00198 0.9009 452 6 151.5 12043 0 65:3 0 8063 14606 480 5661 0 0200 0 8172 464 4 739 4 1203 7 0.6645 0 7666 14513 490 621.4 0 0202 0 7423 476 0 7268 1202.li 06766 0 7653 1.4419 500 680 6 0 0201 0 6749 487.6 713 9 1201 7 066F? 0 74M l.43 5 520 812.4 0 0209 0.5594 SI 1.9 686 4 1194.2 0 7130 0 7006 3.4 IM 540 962.5 0.0215 0.4649 5%6 6%6 1193.2 0.7374 0.6%6 1.3942 560 1833.1 0.0221 0.3868 M22 624.2 1866 4 0 7621 0 6121 1.3742 ,
580 1325 8 0 0:26 0.3217 586.9 548 4 1877.3 0.7872 0 5659 1.353:
600 1542 9 002% 0.2666 610.0 546 5 1865.5 0 8131 0.51 % I.3307 620 1786.6 0 0247 0.2201 646 7 503 6 1150.3 0.8396 0 4664 1.3062 640 2D59.7 0 0260 0.1798 678.6 452 0 1130.5 0.8679 0.4110 1.2789 660 2MS.4 0 0278 0.1442 714.2 390.2 l104 4 0.8987 0.3485 1.2472 680 2708.1 0 0305 0.1115 757.3 309.9 1067.2 0.9351 0.2719 1.2071 700 3093 7 00%9 0 0761 823.3 172.1 995 4 0 9905 0.1484 1.1389 705 4 3206.2 0 0503 0 0503 90: 7 0 902.7 1.0540 0 1.0580 4
9
~ .,..uas. W --- -----'-- - - ' -
48n pouns. Tempotesese.9 See Sei tsee 9 1 W ED 80 M SBD tb my gen 38g0 see, 33p gem, e............ 392 6 452 3 $12A $71A 431.2 480 8 73D 4 000 9 869.5 929.1 988 7 1987A 1 A .. ........... 1890 4 1995.8 lHl.1 1381 IH57 1383 8 6432.8 14827 15H.S 1985.2 66M.7 IM5.7 C l.M i s .............. 28582 2.1853 2.172D ' 2.32M 2.2102 231M 2.3H2 2.392.1 2 4383 2sS625 2. # 52 2.5386 y .............. W.56 R 25 102.26 114.22 lab 16 130.00 190.03 161.93 173.87 185.19 197.71 314
$ A.............. 1948.8 1995.0 1241.2 1288A 1335 4 13834 1432.7 1482A 1533 4 1985.I 16M.7 , 17457 ..
(162.24) a .............. IA788 l.9310 8.9942 2A4M 2A927 2.lMI 2.lM7 2.214n 2.2909 2. 3 51 2.3178 2.3792
,.......... 38.85 4tc0 $1.04 57A5 6303 p Di u to to 95 m.92 92 84 98.84 lie n I0 A........... 1846 6 1893.9 1240 6 1287.5 13351 1383 4 1432 5 14 24 131.1.2 15s5 0 16374 17454 (193.211 s . . .. .. 1.7927 8.8595 1.9872 1.M89 2 0160 20M6 20002 213s t 2iM4 2 2068 2.2413 2.3028
- e. . . . . . 30 53 M 64 38 % 4286 46 94 $1.00 55 07 59 13 63 19 67.25 7537 34 M6 &.. . . . 1892.8 12)9.9 1287.1 13M t 13632 14323 les2 .1 15.43 1 1584 B 1637.5 1745 5 (21220) s ... .. l.8160 1.8743 1.9261 1.9734 2 0:10 2 0576 2.095s 2 1319 21u? 2.1989 2.3603 e... . . . . ...... 22.M 25 43 3 46 31.47 M 47 37.46 40 45 4344 46 42 # 41 S5 ji 30 &..... . .. 1991 4 1239 2 1286 6 13M 4 1382.9 14321 1482 1 1533 0 15s4 7 1637.4 1745 4 (227.h) s.......... .. .... l.7808 8.8396 1.8918 1.9M2 l.9829 2 0235 22615 2 0076 2.1321 2. lH8 2.236)
- e. . . .... ......... 11.040 12 628 14 168 15488 57.19s 18 102 20 20 21.10 23 20 24 H 2748 40 &.. ... .. 1186 I 12 %.5 12848 13331 1341 9 1431.3 1481.4 1532 4 15s41 1637.0 1745I
( 2 7.25) 3. .. 14994 1.M08 1.8140 l.M19 1.9058 1.9467 l.9450 2.0212 20m 2.0843 2.1496
- e. . .. 7.259 8357 9 403 10 427 11.441 12 449 13 452 14 454 15454 16 451 18 446 to A. . . . . . . . 1881 4 12334 1283.0 1331.8 1380.9 1430.5 14a0.8 1531.9 15an n 16M 6 IM4.8 (292.71) s .. .. . .. . . ... ..... 14492 8.7835 1.M7b I.8162 1.8605 1.9015 8.9400 l.942 2 0Hu, 2 04M 2.0049 e . ..... ...... . . . . . . . . . . . . .... 6.230 1.020 1.797 8.M2 9.322 10.077 10 830 11.5m2 12.332 13.830 80 &............. . . . . . . . . . . . . . . 1230.7 1281.1 1330.5 1379.9 1429.7 1480.1 1531.3 15m.1.4 16M 2 lM4.5 (312A3) s .. . . . . . . . . . . . . . . . . . . . l.6791 1.7346 l.78M l.0241 1.8H4 I.9079 8.9442 1.97N7 2.0115 2A731 e .............. . . . . . . . . . . . . . . 4.937 5.589 6.218 6.835 7.446 8A52 86% 9.259 9.840 IIAto ,
000 &............. . . . . . . . . ........ 1227A 1279.1 3329.1 1378.9 1428.9 1479.5 1530.8 1582.9 1635.7 IM4.2 l (32731) s .... .. .... .. . . . . . . . . . . ........ 14518 1.1085 8.7581 l.8029 1.8443 1.8829 1.9193 1.9538 1.9867 2Dess e ...... ...... ...... . . . . 4281 44M 5.l65 5483 5.195 6.102 7.207 7.710 8.212 9.214 g3 &..... . . . ... . . . . . . l224 4 1277.2 1327.1 1377.8 1428 1 1478 8 1530.2 1582.4 1635.3 1743.9 (Mi all a . . . . . . ....
[..... .... [ t A287 [ t ASM [ 1.1310 , 8.1822 , l.8237 , 2.8625 l.8990 1.9335 8.9664 2.0281
[..
- e. . . . . . . . . . . . . . 3 468 3.954 4 413 4.861 5.301 5.738 140 &........ . . . . . . ...... . 1221.1 1275.2 13M 4* 13M.8 1427.3 6.172 6.804 7A35 7ue (353.021 a . .. .... . 1478.2 1529.7 1581.9 1634.9 1741 4
. . . . .. ... . 14087 1.2 83 1.7190 1.M45 I.0063 f.8451 1.8817 8.9163 1.9493 2 Allo O e. . . . . .. . . . . . ...... 3.008 3 443 3 849 4.244 160 &.. 4 631 5.015 5.396 5.775 6.152
. .. ....... 1217 6 1273.1 6.90s.
1325 0 1375 7 1426 4 1477.5 1529.1 (M3.531 s . 1 %I .4 16M $ l743.2 1.590b I.6519 1.1033 1.7491 1.7911 8.8301 1.8667 1.9014 1.9344
- e. 1.9962
. .. . . . . . . . . . . . 2A49 3.044 3 4II 3.M4 4.I10 180 a . .. . .... . . ..... . . . . . . 1214.0 1271A 1323.5 13M.7 1425.6 4.452 1448 4.792 5.129 5466 6.IM (373 A6) s . . . . . .. .. 1528 4 1581.0 1634.1 1742.9
. . . . . . . . . . . . . I.5745 14373 1.6894 1.7355 8.77M 1.8167 1.0534 1.8882 1.9212 1.9831 e.. .. .. . . . . . . ..... 2.Mi 2.726 3.060 3.380 20 4. 3.693 4.002 4.306 4 613 4.917
.. . . .. . 1210.3 1268 9 5.521 1322.1 1373 6 1424.8 1476.2 1520 0 (MI .79) s... . . . . . .. 1.5594 14240 16767 1.7232 1580.5 1633.7 IN24 1.M55 1.0048 1.8415 IJM3 1.9094 1.971) e...... . . . . . 2.125 2.465 2.772 3 066 3.352 3 634 3 983 4.198 230 4. 1306.5 4 467 5A17
. ......... . 1266.7 1320.7 1372 6 1424 0 1475.5
! (Mt.46) s..... 1527.5 1580.0 1633.3 IN2.3
. . . . . . 1.5453 I6117 1.M52 1.7130 1.7545 1.7939 1.830s 1.86M l.8987 1.9607 e l.9276
. . .. 2.247 2 533 2 8064 3.066 3 327 3.584'
{ 240 &. 3.8)9 4 293 4.597
. . .. . . 12025 12645 131'9.2 1371.5 14232 1474 8 1526 9 j (M7.37) s. . .. . .. l.5319 14003 1654o 1.70l7 1579.6 1632.9 IN20 1.7444 1.7839 1.8209 1.4558 1.8889 i I.9510 (
e.... .. .. ... . . . . .... .... 2.063 2.330 2582
- 300 2 m27 3.067 3.305 3.541 3.7M 4.242 I
&........ ...... .. ...... IM2.3 1317.7 1310 4 1422.3 14N.2 iNl.1 1526.3 1579.I
( 4 4.42) s........ . . . . . . . . . ......... ......... 1.5897 iA447 14922 1.7352 f.7N8 1632.5 1.8II8 13467 1.8799 l9430 e........... l.9047
. . . . . . . . . . . . . . . .. ...... 2.1% 2.M2 2421 2.845 3.066 30 &............ .... .... . . . . . . . . 1200 0 1316.2 iM94 1421.5 3.286 3.504 3.9 34 1473.5 1525.8 (4llAS) s.. ........ . . . . . . . . ......... ......... l.5796 14354 IAEN 1.725 1.M62 1578 4 1632.1 INI4 1.8033 12383 f.8716 1.9337 e ......... .... ......... ........ .......... l.M75 2.005 2.227 2.442 2452 i MD &............. 2.859 3.065 3.269 3AN
......... ....... .......... 1360 0 1314.2 1368.3' 1430.6 1472.8 l (417.33) a . . . . . . . . . . . . . .... .... ........ .... .... 1.57U1 14368 1525.2 1578 1 1631.7 iMl.0 1.6751 1.7184 1.7582 8.7954 1.8305 1.8638 1.9360 e.... ... .... ......... ........ 1.4923 HD & ... . .......
.. ...... 1.10 % 1.8980 2 054 2.3u 2.445 2 422 2.788 3147
......... 1251.5 2 . . . . . . . . .......... 1310.9 IMS.5 1418.5 1471.1 1523.8 1577.0 1630.7 (431.72) s............ .......... ........ l.5481 1740.3
.......... 1.8070 1.4M3 1.1002 1.M03 1.7777 1.8130 I.8463 1.9086
- e........... ... ..... ........ ......... l.2851 1.4710 14908 1.8161 8.9M7 2.134 i 400 &............. .......... ........ ......... IM5.1 1306 9 iM27 14le 4 14H 4 1522.4 2.200 2 445 2.15l (444.591a............ 1575.8 86294 17M.5
......... l.5281 1.58D4 1AMS IAS42 1.7247 1.M23 0.7977 1.831I 1.8916 l
1 (Units Are Arbitrary)
= - y .&
b' Y
i 5
15 - u %
[ 0 4
d 0 10
$P*
vt 34 co r
=
5
} . . . . , , ..
2 3 4 5 s y g 1
Pump Speed (Units Are Arbitrary)
Figure 6.2-3. Pump Laws i
I
....c,,_.,. .
- Page 154 - .
SURFACE UTILIZATION Vs FLOW i l 100
\ \ '. .
80 \ <
\ \\ \
Su erheat 60 \
- j
.N
\ .-
\ _
l /
.I ,o \ \ -
20 X
N
" ~-
%W 9 r -
~
ucleate Boiling 0
0 to 40 60 80 100 Full Lead. %
i FIGURE 43
-VoR7.sHEtt 11- _tNCt0 star 2 (Page 1 of 2)
- EST1 MATED CRITICAL SORON CON 0EhTRAT10N
' 532*F, et n, No Renon, No control Rods.
REFERENCE CONDITIONS:
Equilibrius Samarius
- 1. Fuel Resetivity
- a. Core Burnup 200 trro -
,t fg
- b. Read Curve 3.1 of OP-103, Plant Curve look.
- 2. Renon Reactivity (Use Step 2.1 or 2.2) 2.1 value calculated by SA10N I (submit printout).
( I ak/k) = I ok/k OR 80khrs,
- s. Last power level was 100 t n for 2.2 ,
- b. Time Shutdou 24 hre.
l
- c. If time at last power level was < 40 hrs. and SAKON is unavailable, consult with Reactor Specialist.
( _I ak/k)
= I ak/k
- 3. Samarius Resetivity Buildup After Shutdown value calculated by SAK0N I (submit printout) I ak/k 3.1 4 Reactivity Rffect From Temperature
- a. Average RC Temperature 8 3 8 #F l
- b. Reference temperature is 5320F.
Temperature coef ficient at ppm 3 is obtained c.
from Curve 3.6 of OP-103, Plant Curve Book, to be z 10-21 Ak/k/oF.
- d. Reactivity = [T(ave) - 532] ITemp. Coef f. ]
i e. Reactivity =( -
)( z 10-21 ak/k/or)= 1 ak/k l l
- 5. Raaetivity of control toda at Desired Insertion Groups 1-4 at 100 I VD Group 5 at Joe 1 WD Croup 6 at see 1 WD 50 1 WD Regulating Group Worth I ak/k
- Group 7 at I ak/k Croup 8 Worth Group 8 at _ to 1 WD Calculated By Date l
i Date 11/16/82 Page 18 CP-210 Rev. 16
rigure ao 41
- a. . C*
_L 1
^1
- Fuel Ass.
- Fuel A ss.
6- c.
.] L M 't
- r ,/ hu. */"I oss,
f A
- y: m in OC h i1.eusg..........
ll et 3 ....., g "
GlD ! j $$ .
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E
" "' 'E W.f,,m,,'.,,
6 y.1D ! . ..., @$.ED @; 06
- p :
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,......L.Q 4
O / M.Q =,, 6W _ns 3
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a
- *= cap _
- t }e,, ,
o i-a .. . , ,,. n .io . -
. 14 ,
{a k {u , 27 ;
ta s u p=
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4)
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, gr =" "-
g Whh j
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QW g 46gi.a ,-.m 5
=N tscuasectn
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- l. . . .!:.,.. r..!,=.
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'%iWWW%
I c.oy S
d# 00 Date 06-03-83 AP-380 ESSA REV FOLLOW-UP (Cont'd)
DETAILS ACTIONS -
NOTE
e Seal injection e Pump start permissive e Seal return e Power available e SW cooling e RC PRESS and TEMP above RCP AND: curve Enclosure 1.
- a. IF,OTSGs available.
THEN start 1 RCP in each loop NOTE
,) OR start 2 RCPs in one TEop RCP-1B is preferred.
S3.
- b. IF OTSGs NOT available.
--- IF RCPs NOT available,
~-~
THEN start one RCP. Natural THEN refer to AP-530 UTrEulation.
Page 9 of 25 ESSA AP-380 J
,e g
O ESSA REV 00 Date 06-03-83 AP-380 EMCLOSURE 1 RCP CURVES 1000 i i i i i i i , t 900 -
800 -
@ 700 IRCP I
h600 - -
m O y500 - -
c.
o et 400 -
300 - -
2 RCP 200 -
OPERATION 10 0 - -
I ' ' ' I I I I O !
O -
100 200 300 460 500 RC TEMP,TC( F)
AP-380 Page 25 of 25 ESSA O
F L;:(
- - ' - - =
E0LLOW-UP (C'ont'd)
ACTIONS DETAILS
-^
1,8 Refer to Figure 1.
o F in Region 2 go to Step 1.9 o n Region 3
'1EN go to Section 2.0 M AD > 1400')
o "F in Region 4 TEN go to Section 3.0 N AD > 1800')
, _ _ _ _ _ _ ____ -m - -- --
, - - - - - ----- - -----------1 Figure _1 CORE EXIT FLUID TEMPERATURE FOR l
INADEQUATE CORE COOLING tsoc , , , , .,,,
asoc - f -
-SAT LINE 220c REGION
~
j i 1 200C - Si4co
- ~
.' 800 REGicN l isoc-g isoo - -
i I taco- "f" -
s REGeoN E coo -
4 i soc - -
500 - Tegio >isco 4o0 i
2%
400 500 800 ', N300 1200 CCEE THIRNCCOUPLE TEW (*l'i a
---- - ^ - -- ^---
, Page 7 of 20 ICC
=
i 1
. l
l TABLE 3.3-1 REACTOR PROTECTION SYSTEM INSTRUMENTATMN4 /
O MINIMUM u TOTAL NO. CHANNELS CHANNELS APPLICABLE TO TRIP OPERARLE MODES ACTlON r-FUNCTIONAL UNIT OF CHANNELS i 2! 'i
< ',1, 2 and
- 8 j l. Mandl Reactor Trip I i I Q 2#
- 2. Nuclear Overpower 4 2 3 1, 2 l 38 1, 2 I 3
-t
- 3. RCS Outlet Temperature - High 4 2 3 w 4. Nuclear Overpower Based on RCS Flow and AXIAL POWER IMBALANCE -
4 2(a) 3 1, 2 2#
- 5. RCS Pressure - Low 4 2(a) 3 1, 2 3#
- 6. RCS Pressure - High 4 2 3 I, 2 3#
- 7. Variable Low RCS Pressure 4 2(a) 3 1, 2 38 l
Y 8. Reactor Containment Pressure - High 4 2 3 I, 2 3#
1 y 9. Intermediate Range, Neutron Flux w and Rate 2 J 2 1, 2 and
- 4
- 10. Source Range, Neutron Flux and Rate A. Startup 2 0 2 2## and
- 5 B. Shutdown 2 0 1 3, 4 and 5 6 II. Control Rod Drive Trip Breakers 2 per trip i per trip 2 per I, 2 and
- 7#
system system trip system
- 12. Reactor Trip Module 2 per trip I per trip 2 per I, 2 and
- 7#
g system system trip system
- 13. Shutdown Bypass RCS Pressure - High 4 2 3 2**,3, 6#
l j
- 14. Reactor Coolant Pump Power Monitors 2 per pump 1.from 2 2 per pump 4.,5==
1, z 23
] or more d
o, , pimps (a,b) s x
G e.. ._
e -
TABLE 3.3-1 (Contirvand)
TABLE NOTAT!M
- With the control rod drive trip breakers in the closed position and the control rod drive systehrcapa'ble of rod withdrawal.
- When Shutdown Bypass is actuated.
- The provisions of Specification 3.0.4 are not applicable.
- High voltage to detector may be de-energized above 10-10 amps on both Intermediate Range channels.
(a) Trip may be manually bypassed when RCS pressure < 1720 psig by _
l actuating Shutdown Bypass provided that: l 1
(1) The Nuclear overpower Trip Setpoint is 13% of RATED THERMAL )
POWER, -
. l (2) The Shutdown Bypass RCS Pressure - High Trip 5etpoint of 11720 .
psig is imposed, and (3) The Shutdown Bypass is removed when RCS pressure > l800 psig. ,
(b) Trip may be manually bypassed when reactor power is less than or equaJ to ,_
2475 MWt and 4 reactor coolant pumps are operating.
ACTION STATEMENTS ACTION 1 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the control rod drive trip breakers.
ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provideAafl oi the following conditions are satisfied:
- a. The inoperable channel is placed in the tripped condition within l'
one hour.
- b. The Minimum Channels OPERABLE requirement is met; l however, one additional channel may be bypassed for up to 2 1
' hours for swveillance testing per Specification 4.3.1.1.
il il lO i
CRYSTAL RIVER -UNIT 3 3/4 3 3 Amendment No.F,X, JJ,56 I i
TA8LE 3.31 (Continued)
ACTION STATEMENTS (Continued) and the' inoperable channel above say be by-passed for up to 30 minutes in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period when necessary ta test the trip breaker associated with the logic of the channel being tested per Specification 4.3.1.1. and
- c. Either, THERMAL POWER is restricted to < 75t of RATED RATED THEPJEL and the Nuclear Iver-power Trip 5etpoint is reduced to y,,85% of RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or the QUADRANT POWER TILT is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTICN 3 - With the number of OPERABLE channels one less than the Total Number of Channels STARTUP and POWER OPERATION may proceed provided both of the following conditions are satisfiec: ~
I
- a. The inoperable channel is placed in the tripped condition within one hour. ,
- b. The Minimum Channels OPERABLE requirement is met; however, one additional channel any be -
bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1, and the . .
inoperable channel above may be bypassed for up to 30 siinutes in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period when necessary to test the trip breaker associated
- witn the logic of the channel being tested per 5pecification 4.3.1.1.
Action 4 - With the num6er of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL Power lev'el:
- a. < 5% of RATED THERMAL POWER restore the inoperable channel to f DPERABLE status prior to increasing THERMAL POWER above 5% of l -
RATED THERMAL POWER.
l
- b. >5% of RATED THERMAL POWER, POWER OPERATION may continue.
l
[
- CRYSTAL R:VER - UM:73 3/43-4 Amendmenc No. 55 h e
e
1 m
2400, cumvt -
3 puma i
~
9 2200 .
E w '
i '
i .
W . :
- : -cumvt i .
i j .
- Pump ,
- a. ,
e
- 2000 '
_l 8 -
I
. : i e , '
s o ,
j u .
I ' .i i .
1800 '.
/ -
i ! !
t l i
- i .
580 GCC 620 640 nt Acron Qui'.ti itM*tMa~unt.
- REACTCR CCCL ANT FLOW 8 UMPS CPERATING
- CyevE FLOW */. Q E31GN1 SQWEM (R*M (7YSE QF (IMl?)
I 135.7 s ICS (10 4.5 % ) 113.0 5 % 4 PWMP5 (CNER) 2 104.4 x 10 " ( 79.6 %) 90.84 % 3 PUMPS (DNER)
- PRES 5URE/ TEMPERATURE LtWITS AT MAXIMUM ALLOWABLE PCWER FCR MINIMUM CNER BA SE3 FIGUME 2.1 CRY 3?AL RIVER UNii 3 323 Amendment No. M.Jfl 41 Fc g 2_
K p , , , - - - -,,,,,,nw ,--n,-,,.,,,-.----,- ._-w- ---,---.,,,,,_,-,,---n,.,_w,-
- e 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVE!LLANCE REQUIREMENTS
\
3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION l
3.0.1 Limiting Conditions for Operation and ACTION requirements shall
~
be applicable during the OPERATIONAL EDES or other conditions specified ,
for each specification. l l
3.0.2 Adherence to the requirements of the Limiting Condition for Oper- '
ation and/or associated ACTION within the specified time interval shall constitute compliance with the specification. In the event the Limiting Condition for Operation is restored prior to expiration of the specified time interval, completion of the ACTION statement is not required. l l
3.0.3 When a Limiting Condition for Operation is not met, except; as provided in the associated ACTION requirements, within I hour action shall be initiated" to place the unit in a MODE in which the Specification does not apply to
, placing it, as applicable, in:
- 1. At least HOT STAND 8Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,
- 2.
At least HOT SHUTD0WN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and,
- 3. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Where corrective measures are completed that permit operation under the ACTION
(' requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation.
Specifications.
Exceptions to thes's requirements are stated in the individual 3.0.4 Entry into an OPERATIONAL EDE or other specified applicability condition shall not be made unless the conditions of the Limiting Coni dition for Operation are met without reliance on provisions contained in !
the ACTION statements unless otherwise excepted. This provision shall I not prevent passage through OPERATIONAL MDES as required to comply with I ACTION statements. !
I 3.0.5 When a system, subsystes, train, component or device is determined to ,
be inoperable solely because its_ emergency _ power source is inopoeable, or' solely because its normal power source is inoperable, it may be considered OPERA 8LE fqr the purpose of satisfying the requirements of its applicable Limiting Condition for Operation', provided: (1) its corresponding normal or emergency power source is OPERABLE; and (2) all of its redundant system (s),
, sybsystes(s), train (s), component (sVand device (s) are OPERA 8LE, or likewise satisfy the requirements of this specification. Unless both conditions (1)'
and (2) afe satisfied, within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> action shall be initiated to place the unit in a MODE in which the applicable Limiting Condition for Operation does not apply by placing it as applicable in:
- 1. At least HOT STAND 8Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,
, 2. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and
( ,
- 3. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
This Specification is not applicable in MODES 5 or 6.
! CRYSTAL RIVER - UNIT 3 3/4 0-1 Amenenent No. 40 l
EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - T..._ > 280*F
=Ty LIMITING CONDITION FOR OPERATION -
~
3.5.2 Two independent ECCS subsystems shall be OPERABLE with each subsystem comprised of:
- a. One OPERA 8LE high pressure injection (HPI) pump,
- b. One OPERA 8LE low pressure injection (LPI) pump.
- c. One OPERABLE decay heat cooler, and
, d. An OPERA 8LE flow path capable of taking suction from the borated water storage tank (BWST) on a safety injection signal and manually transferring suction to the containment sump durirg the recirculation phase of operation. ~-
APPLICABILITY: MODES 1. 2 and 3. .
ACTION: *
{ a. With one ECCS subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within, the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- b. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.
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CRYSTAL RIVER - UNIT 3 3/4 5-3 -
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! 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES OPERATING LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE:
- a. Two physically independent circuits between the offsite trans-mission network and the onsite Class lE distribution system, and
- b. Two separate and independent diesel generators each with: '
- 1. A separate day fuel tank containing a minimum volume of 403 gallons of fuel, .
- 2. A separate fuel storage system containing a minimum volume of 20,300 gallons of fuel, and - -
I 3. A separate fuel transfer pump.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
- a. With either an offsite circuit or diesel generator of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirements 4.8.1.1.1.a and 4.8.1.1.2.a.4 within one hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter; restore at least two offsite circuits and two diesel generators to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STAND 8Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- b. . With one offsite circuit and one diesel generator of the above required A.C. electrical power sources inoperable, demonstrate the OPERA 81LITY of the remaining A.C. sources by performing Surveillance Requirements 4.8.1.1.1.a and 4.8.1.1.2.a.4 within one hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter; restore at least one of the inoperable sources to OPERABLE status within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or be in at least HOT STAND 8Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Restore at least two offsite circuits and two diesel generators to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from the time of initial loss or be in at I. least HOT STAND 8Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
CRYSTAL RIVER - UNIT 3 3/48-1
1 ELECTRICAL POWER SYSTEMS ACTION (Continued)
- c. With two of the above required offsite A.C. circuits inoperable, 4
demonstrate the OPERABILITY of two diesel generators by perfonning Surveillance Requirement 4.8.1.1.2.a.4 within one
- hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter, unless the diesel generators are already operating; restore at least one of the inoperable offsite sources to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
With only one offsite source restored, restore at least two offsite circuits to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from time of initial loss or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />..
- d. With two df the above required diesel generators inoperable. -
demonstrate the OPERABILITY of two offsite A.C. circuits by perfoming Surveillance Requirement 4.8.1.1.1.a within one
- hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter; restore at 2
least one of the inoperable diesel generators to OPERABLE ,
i status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least HOT STANDBY within the ,
next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and. in COLD SHUTDOWN within the following 30 r hours. Restore at least two diesel generators to OPERABLE .
status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from time of initial loss or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SuitVEILLANCE REQUIREMENTS 1
1 4.8.1.1.1 Each independent circuit between the offsite transmission network and the onsite Class 1E distribution system shall be:
- a. Detennined OPERABLE at least once per 7 days by verifying;
- 1. (orrectbreakeralignmentsandindicatedpoweravailability, and i 2. That the sump pumps in the tunnel containing the DC control feeds to the 230kv switchgear are OPERABLE.
} b. Demonstrated OPERABLE at least once per 18 months during shutdown by transferring unit power supply from the nomal circuit to the alternate circuit.
CRYSTAL RIVER - UNIT 3 3/4 8-2
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_ M A-srER_ Kay ANSWERS-SECTIONp 5.1 b. Ref: CR3 HTFF pp. 148-156 (1.0) 5.2 a. Ref: 1. Duke Power Company, FNRE; pp. 115-120 (1.0)
- 2. NETRO, 12.1-4 5.3 b. Ref: 1. OP-210, Rev. 16, p.8 (1.0)
- 2. NUS, NETRO, Unit 6
- 3. Westinghouse Reactor Physics, Sect. 3 & 5 5.4 a. Ref: NETRO, p. 10.3-2 (1.0) 5.5 d. Ref: NETPP, p. 6.2-5 (1.0) 5.6 c. Ref: NETPP, p. 6.4-5 (1.0) 5.7 b. Ref: CR3 HTFF p. 151 , (1.0) 5.8 c. Ref: 1. Westinghouse NTO, p. I-5.77 (1.0)
- 2. NETRO, 10.5-2
- 3. Duke Power Company, FNRE; p. 169 5.9 a. More Inserted (50% equil Xe; ++) (2.0)
- b. More Inserted (Xe free; + +)
- c. More inserted (535 - 532F)
- d. More Inserted (difference .35%, Curve 3.9)
Ref: OP-210 and OP-103 5.10 a. Ref: Water Box Primary System, ANAO-29, p.2 (1.0) 5.11 b. Ref: ICS: R0-103, p. 53 (1.0) 5.12 a. Ref: ICS, R0-103, p. 5 (1.0) 5.13 d. Ref: TS p. 3/4 1-2 (d is p. 3/4 2-1) (1.0) 5.14 c. Ref: Duke Power Company, FNRE, p. 124-128 (1.0) 5.15 b. (1.0)
Ref: Power System Operation (1.0)
R. H. Miller, p. 22-24
2 5.16 b. Ref: TS p. B 3/4 1-1 (1.0) 5.17 d. Ref: JTS 0 0 4 Oco gs {)P o r-oc-sfs- SY-M D C. (1.0) p>)to4-ll 5.18 a. Ref: Duke Power Co., FWRE pp. 200 & 221 (1.0) 5.19 b. Ref: Duke FNRE, pp. 253-257 (1.0) 5.20 1. Control rods in a single group move together (1.5)
( 1 1 6.5% deviation)
- 2. Reg. groups are sequenced with overlap as required.
- 3. Reg rod and APSR insertion limits are maintained.
Ref: Power Dist. Design Criteria,1984, J. P. Haerle 5.21 a. True, p. 10 (2.0)
- b. True, p. 2 4
- c. True, pp. 2-3 ,
- d. False, p. 7 Ref: Analysis Summary in Support of an Early RC Pump Trip B&W Submittal, August 24, 1979.
5.22 To assure that certain potential faults (such as a seismically (0.5) induced fault high signal) will not prevent this instrumentation from providing the protection action.
Ref: TS p. B 2-7 5.23 b. Ref: CR 3 Draf t HTFF/Thermo, p. 82 (1.0) l l
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3 ANSWERS - SECTION 6 6.1 b. Ref: ANO-91, p. 6, Rev. 0 (1.0) 6.2 d. Ref: ANO-10-', pp. 1, 11, and 14 (1.0) 6.3 b. HP flash tank is correct, MSRLP flash tank is wrong (1.0)
(p. 15) (a); 1A/B, 2A/B heaters do not have non-return valves, pp. 19 & 20 (c); only on 1A/B, 2A/B heaters, pp. 18 & 19 (d).
Ref: NAO-99, pp. 15-20 6.4 c. Ref: STM-12-9 (1.0) 6.5 c. Ref: JTM 28-4 (1.0) olG 6.6 1. UpperThrustggaringCooler (1.0)
- 2. Lower Guide % earing Cooler
- 3. Motor air cooler
- 4. Seal Area Cooler Ref: STM-23-7 and 8 6.7 a. Ref: STM 17-10 and 12 (1.0) 6.8 b. Ref: STM 10-4 and 5 (1.0) 6.9 c. Ref: PASS lesson plan R0-105 p. 8 (1.0) 6.10 b. (1.0)
- a. 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 9 nameplate rating
- c. 1-AC, 1-DC
6.12 1. Open DHV-11 and 12 (LPI to HPI cross connects) (0.33 each) (1.0)
- 2. Close MUV-58 & 73 (BWST Suction valves)
- 3. Open DHV-42 and 43 (RB purp suction valves)
- 4. Close (BSV-36 & 37) (NA0H tank outlet valves) - (Not required)
Ref: STM 4-9 thru 12
4 6.13 b. Ref: STM 13-2 (1.0) 6.14 a. Ref: STM 6-4 (1.0) 6.15 b. Ref: RPS Handout, p. 21 (1.0)
NOTE: State lamp - auto reset deadband set for maximum 6.16 c. Ref: CR Requalification Fuel Handling Lesson Plan (1.0)
- p. 13, Rev. 1 6.17 d.'* Ref: OP-504, p. 8, Rev. 7 (1.0)
STM 27-56 6.18 'A' 'B' (2.0)
- a. Main FW Block Valve (FWV-30 FWV-29) (0.25 ea.)
Lo-Load (FWV-31 FWV-32)
Startup " "
(FWV-36 FWV-33)
Emergency " (FWV-35 FWV-34)
Emergency Bypass Valve (FWV-162 FWV-161)
MFWP Suction Valve (FWV-14 FWV-15)
FW Crosstie (--------FWV-28--------)
MSIVs (MSV-411, 412 MSV-413, 414)
- b. 1. Affected OTSGs pressure has recovered to >725 psig (1.0)
- 2. Rupture matr.ix is bypassed Ref: CR SLRM handout 6.19 c?' R bef: STM 15-10 (1.0) g\t.Y --0.20 d Rf. ST" 10 '? * 'a (1.0) 6.21 b. Ref: STM-22, pp. 22-25 (1.0) 6.22 b. Ref: STM 41-4, 5 (1.0) 6.23 c. Ref: Fuel Handling, Requal Training, p. 18 (1.0) i 4
- , - , . - - . --i . _ _ _ . . - _ ,- - - .c 7 ------- _ _ ,
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5 ANSWERS - SECTION 7 7.1 a. NONE (AP-241) (2.5)
- b. 1, 2, 3, 7, 8 (AP-242) (0.5 each)
- c. 3 (AP-243)
- d. 2 (AP-244)
- e. 4, 5, 6, 7, 9 (AP-245) 7.2 1. Notify AB operator to ensure V-90 closed (0.25)
- 2. Notify TB operator to stop SOP-7 (0.25)
Ref: AP-277, pg. 2, Rev. 00 7.3 a Ref: AP-320, p. 2, Rev. 00 (1.0) 7.4 1. Bypass ES Actuation (.33 each)
- 2. Return ES equipment to STBY status
- 3. Go to VP-580 Ref: AP-380, p. 3, Rev. 01 7.5 1. Ensure both MFPs tripped (2.0)
- 2. Ensure closed: MBVs LLBVs SUBVs
- 3. Ensure both EFWPs start
- 4. Ensure emergency feedwater block valves open
- 5. Close FWV-162 (A OTSG)
FWV-161 (B OTSG)
Ref: AP-450, Rev. 1 7.6 d Ref: OP-502, p. 4, Rev. 13 (1.0) 7.7 c Ref: AP-380, p. 9, Rev. 00 (1.0) 7.8 b Ref: AP-501, p. 3 (1.0) 7.9 b Ref: OP-501, p. 2, Rev. 7 (1.0) 7.10 a Ref: EP-120, p. 2, Rev. 00 (1.0) 7.11 a Ref: OP-504, p. 15, Rev. 7 (1.0) 7.12 b. Ref: OP-605, p. 3 & 4, Rev. 28 (1.0) 7.13 a. Ref: Fuel Handling Lesson Plan, pp. 25 & 26, Rev. 1 (1.0) 7.14 d. Ref: Fuel Handling Lesson Plan, p. 31, Rev. 1 (1.0) 7.15 d. Ref: OP-210, Step 4.9 (1.0) t
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6 7.16 a. Ref: OP-210, Step 4.14 (1.0) 7.17 b. Ref: OP-402, Rev. 41, Step 4.11 (1.0) 7.18 1. Ensure all feeder BKRs to affected bus are open. (1.0)
- 2. Close feeder BKR from Units 1 and 2 by holding in "Close" position for 10 seconds:
'A' bus BKR 3211
'B' bus BKR 3212 Ref: AP-770, p. 2, Rev. 00 7.19 b Ref: RP-101, p. 5, Rev. 19 (1.0) 7.20 b Ref: RP-101, p. 23, Rev. 19 (1.0) 7.21 b Ref: 10CFR 20.101, p. 239, Rev. 1/1/85 (1.0) 7.22 e Ref: EP-290, p.-7, Rev. 02 (1.0) 7.23 b. Ref: OP-412, Rev. 29, pp. 2-9 (1.0)
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ANSWERS - SECTION 8 8.1 d. Ref: TS 3/4 3-3 and 3-4 (1.0) 8.2 b. Ref: TS p. 3.2.4 (1.0) 8.3 a. Ref: EM-201, Rev. 4, p. 1-4 (1.0) 8.4 b. Ref: AI-100, Rev. 7, p. 7 (1.0) 8.5 b. Ref: AI-500, Rev. 46, p. 10 (1.0) 8.6 a. Ref: EM-202, Rev. 19, p. 3 (1.0) 8.7 b. Ref: EM-205, Rev. 8, p. 6 (1.0) 8.8 c. Ref: EM-207, Rev. 16, p. 5 (1.0) 8.9 a. False (0.5)
- b. False (0.5)
Ref: FP-601, Rev. 17, p. 4.
8.10 c. Ref: FP-601, Rev. 17, p. 6 (1.0) 8.11 a. False, p. 3/4 1-1 (0.5)
- b. False, p. 3/4 1-20 (0.5)
- c. True, p. 3/4 5-1 (0.5)
- d. False, p. 3/4 0-2 (0.5)
Ref: TS, pp. noted above 8.12 c. Ref: OSIM III-10, Rev. 8 (1.0) 8.13 b. Ref: OSIM VI-9, Rev. 22 (1.0) 8.14 a. Ref: TS pp. 2-2 and 2-3 (1.0) 8.15 b. Ref: <TS pp. 4-5, 1-16, 5-1, 1-14 (1.0) 8.16 d. Ref: 1. TS p. 3/4 0-1 (1.0) 8.17 c. Ref: TS 3/4 1-1 (1.0) 8.18 a. Ref: TS p. 3/4 4-24 (1.0) 8.19 d. Ref: TS p. 3/4 5-2 (1.0) e
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8 8.20 a. Must obtain a qualified relief operator at the controls (1.0)
- b. He remains within the confines of the control center (.5) and (1.0) maintains an unobstructed view of the operational control panels. (.5)
Ref: OSIM p. III-2 8.21 a. SOTA (.2) (1.0)
Nuclear Operations Superintendent (.2)
Person-on-call (.2)
NRC (red phone) (.2)
NRC Resident Inspector (.2)
- b. Completes steps 1 - 9 (1.0)
Assigns next consecutive report number Forwards it to Nuc. Ops. Sup. for disposition 8.22 1. A red tagged item in other than the specified condition (1.0)
- 2. A blue tagged item issued to any person other than the 550D.
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ENCLOSURE 4 REQUALIFICATION PROGRAM EVALUATION REPORT Facility: Crystal River Unit 3 Examiner: Sandy Lawyer Date(s) of Evaluation: May 14-16 and July 9-11, 1985 Areas Evaluated: X Written X Oral Simulator
- 1. Evaluation of Examination Both of these written examinations were totally written and administered to all candidates by NRC. This portion of the evaluation is therefore N/A.
- 2. Evaluation of facility examination administration: N/A
- 3. If NRC examination was substituted for facility examination (or sections thereof), attach examination summary sheet to this form.
Summary sheets attached X:
- 4. Evaluation of examination grading: N/A Oral Examination - NRC administered orals
- 1. Overall evaluation Satisfactory
- 2. Number observed N/A Number conducted 21 Number passed 21 Simulator Examination
- 1. Overall evaluation N/A
- 2. Number observed Number conducted Overall Program Evaluation Satisfactory Marginal X Unsatisfactory (List major deficiency areas with brief descrip-tive comments)
Areas of deficiency identified by the NRC written examinations were Controls and Instrumentation (Section 3), Procedures (Sections 4 and 7), and Administrative Conditions and Limitations (Section 8).
( .m
.f' Enclosure 4 2 In accordance with Examiner Standard ES-601, the March 1985 Requalification Program Audit resulted in an Unsatisfactory rating while the combined audits of May and July 1985 resulted in a pass rate of 71% which is considered Marginal.
It was expected that the accelerated retraining program, conductei since March, would have resulted in a pass rate of greater than 80% and thus, a Satisfactory rating. The licensee is to identify corrective action and discuss their program re-evaluation in the near future.
e ubm t Forwarded: Approved:
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. Mwyer y f.~A. Wilson